Research on confinement improvement under optimized injection time of electron cyclotron resonance heating power at EAST

• DOI: 10.1088/1361-6587/adbd72
• Publication Date: 2025-03-06T22:52:36Z
• Authors: Z H Wang; B Zhang; X Z Gong; J P Qian; W Wang; Y T Guo; W B Liu; P Li; Q L Wang; Y C Hu; T Q Jia; R Z Chen; Z F Guan; W Y Lu; C Cao; L Q Xu; Q Zang; S X Wang; Z C Lin
• Keywords: Electron cyclotron resonance; Cyclotron resonance; Plasma confinement

Abstract A primary objective of the Experimental Advanced Super-conducting Tokamak (EAST) is to demonstrate steady-state long-pulse high-performance plasma operation for future large-scale devices like ITER and CFETR[1]. The formation internal transport barriers (ITBs) one key issues achieve operation. Optimizing current density profile promising ways improve confinement which beneficial ITBs. Much endeavour has been dedicated optimize in EAST over recent years.
In this paper, authors discuss ITB leading significant improvement by optimizing injection time electron cyclotron resonance heating (ECRH) power on EAST. After ECRH delayed injection, poloidal beta (\beta_P) thermal energy (H_{98y2}) was observed increase. distribution changed deposition showed an off-axis trend. analysis soft X-ray (SXR)[2] Electron Cyclotron Emission (ECE)[3] diagnostics data that structural strength Magnetohydrodynamic (MHD) significantly decreased core region at case. turbulence growth rate calculated Global Linearized Fusion (TGLF) code[4] also shows trapped mode (TEM) stabilized.