The effect of impurity seeding into the closed divertor on plasma detachment in the HL-2A tokamak. (1st March 2023)

• Record Type: Journal Article
• Authors: Gao, J.M.; Cai, L.Z.; Cao, C.Z.; Ma, H.C.; Ke, R.; Wu, N.; Hu, Y.; Gao, X.Y.; Cui, C.H.; Huang, Z.H.; Nie, L.; Liu, L.; Yang, Z.C.; Yu, X.; Li, Y.G.; Jiang, M.; Xue, G.Q.; Zhong, W.L.; Wu, T.; Shi, Z.B.; Yan, L.W.; Ji, X.Q.; Xu, M.
• Is Part Of: Nuclear fusion. Volume 63:Number 3(2023)
• Publication Date: 2023-03-01
• Subjects: closed divertor -- impurity injection -- detachment -- H-mode -- HL-2A; Nuclear fusion -- Periodicals; 621.48405
• DOI: 10.1088/1741-4326/acaf2f
• Languages: English
• ISSNs: 0029-5515

Abstract

Abstract: Recent progress towards an increased understanding of detached divertor physics has been made with the highly closed divertor geometry in HL-2A. Non-intrinsic impurities were injected into the outer divertor chamber, and increased divertor neutral pressure and enhanced volumetric energy loss in the divertor were observed. Meanwhile the neutral pressure in the main chamber decreased slightly, and neutral compression between the divertor and main chamber increased greatly. This led to divertor detachment with a low upstream plasma line-averaged electron density ( ∼ 0.5 n GW ). In the H-mode, slight degradation of the core confinement, characterized by a decrease in plasma stored energy and pedestal pressure and an increase in edge-localized mode frequency, was observed, but the H-mode was still sustained well with H98 > 1. Pedestal density fluctuation was increased during detachment, implying that the enhanced pedestal transport might be responsible for the degradation. During the divertor detachment phase, the impurities were well controlled in the divertor without strong radiation near the X-point region, and the main plasma density did not increase but decreased slightly; this could be a benefit of the highly closed divertor geometry. The experimental results suggest that a closed divertor geometry has the advantages of volumetric energy loss, gas pumping and impurity control in the divertor without significant effects on the plasma confinement, thus giving a wider operating window for divertor detachment.