Investigations on the heat flux and impurity for the HL-2M divertor. (14th September 2016)

• Record Type: Journal Article
• Authors: Zheng, G.Y.; Cai, L.Z.; Duan, X.R.; Xu, X.Q.; Ryutov, D.D.; Cai, L.J.; Liu, X.; Li, J.X.; Pan, Y.D.
• Is Part Of: Nuclear fusion. Volume 56:Number 12(2016:Dec.)
• Publication Date: 2016-09-14
• Subjects: HL-2M -- advanced divertor -- heat load -- impurity -- divertor target geometry -- SOLPS5.0; Nuclear fusion -- Periodicals; 621.48405
• DOI: 10.1088/0029-5515/56/12/126013
• Languages: English
• ISSNs: 0029-5515

Abstract

Abstract: The controllability of the heat load and impurity in the divertor is very important, which could be one of the critical problems to be solved in order to ensure the success for a steady state tokamak. HL-2M has the advantage of the poloidal field (PF) coils placed inside the demountable toroidal field (TF) coils and close to the main plasma. As a result, it is possible to make highly accurate configuration control of the advanced divertor for HL-2M. The divertor target geometry of HL-2M has been designed to be compatible with different divertor configurations to study the divertor physics and support the high performance plasma operations. In this paper, the heat loads and impurities with different divertor configurations, including the standard X -point divertor, the snowflake-minus divertor and two tripod divertor configurations for HL-2M, are investigated by numerical simulations with the SOLPS5.0 code under the current design of the HL-2M divertor geometry. The plasmas with different conditions, such as the low discharge parameters with I p = 0.5 MA at the first stage of HL-2M and the high parameters with I p = 2.0 MA during the normal operations, are simulated. The heat load profiles and the impurity distributions are obtained, and the control of the peak heat load and the effect of impurity on the core plasma are discussed. The compatibility of different divertor configurations for HL-2M is also evaluated. It is seen that the excellent compatibility of different divertor configurations with the current divertor geometry has been verified. The results show that the snowflake-minus divertor and the tripod divertor with d x = 30 cm present good performance in terms of the heat load profiles and the impurity distributions under different conditions, which may not have a big effect on the core plasma. In addition, it is possible to optimize the distance between the two X -points, d x, to achieve a better performance in terms of the parameters of discharges.