文献类型：期刊文献

英文题名：Characterization of beam ion loss in high poloidal beta regime on EAST

作者：Fu, J.[1,2];Huang, J.[1];Wang, J. F.[1];Yu, L. M.[3];Van Zeeland, M. A.[4];Chang, J. F.[1];Hao, B. L.[5];Chen, J. L.[1];Wu, M. Q.[5];Hu, W. H.[1];Xu, Z.[1];Gao, W.[1];Su, J. X.[1,2];Sun, Y. X.[1,2];Liang, R. R.[1,2];Zang, Q.[1];Liu, H. Q.[1];Lyu, B.[1];Zhong, G. Q.[1];Zhang, B.[1];Gong, X. Z.[1]

机构：[1]Chinese Acad Sci, Hefei Inst Phys Sci, Hefei 230031, Peoples R China;[2]Univ Sci & Technol China, Hefei 230026, Peoples R China;[3]East China Univ Sci & Technol, Dept Phys, Shanghai 200237, Peoples R China;[4]Gen Atom, POB 85608, San Diego, CA 92186 USA;[5]Shenzhen Univ, Adv Energy Res Ctr, Shenzhen 518060, Peoples R China

年份：2022

卷号：64

期号：9

外文期刊名：PLASMA PHYSICS AND CONTROLLED FUSION

收录：;EI(收录号：20223112459234);WOS:【SCI-EXPANDED(收录号:WOS:000827832400001)】；

基金：We would like to express our gratitude to Dr BAE Cheonho for the improvement of the English in this paper. This work was supported by the National Natural Science Foundation of China under Grant Nos. 11975276 and 12175272, the National Key R&D Program of China under Grant Nos. 2019YFE03020004 and 2017YFE0300404, Anhui Provincial Natural Science Foundation No. 2008085J04, the Anhui Provincial Key R&D Program under Grant No. 202104b11020003, the Outstanding Program of Hefei Science Center, CAS (No. 2021HSCUE015), the Collaborative Innovation Program of Hefei Science Center, CAS (No. 2019HSC-CIP015). Numerical computations were performed on the ShenMa High Performance Computing Cluster in the Institute of Plasma Physics, Chinese Academy of Sciences. M Van Zeeland's work was supported in part by the U.S. Department of Energy, Office of Science, Office of Fusion Energy Sciences, using the DIII-D National Fusion Facility, a DOE Office of Science user facility, under Awards DEFC02-04ER54698, SC-G903402, DE-AC02-09CH11466, DE-AC05-00OR22725 and DE-SC0010685.

语种：英文

外文关键词：beam ion loss; wall load; confinement; high-beta(p); tokamak

摘要：A critical issue for achieving the integrated operation of steady-state long-pulse high-confinement (H-mode) plasmas on experimental advanced superconducting tokamak (EAST) is to improve beam ion population confinement during neutral beam injection (NBI). To study the characterization of beam ion loss and improve beam ion confinement, the steady-state long pulse scenario discharges were conducted on EAST (beta(p) >= 2.0, beta(N) >= 1.7, q(95) >= 6.7 and H-98y2 >= 1.1) with NBI heating. Based on neutron yield, the beam voltage and line-averaged electron density were adjusted from 50 kV to 60 kV and 4.4 x 1019 m(-3) to 5.0 x 10(19) m(-3), respectively. The results show that the dominant mechanisms of beam ion loss are shine-through loss, prompt loss, and stochastic ripple loss. The shine-through loss fraction is determined by initial velocity, flight time and entire beam path. The change in prompt loss fraction is caused by the change in the deposition of beam ions. The change in stochastic ripple loss fraction is caused by the change in the initial fraction of trapped-confined ions. Detailed physics shows that the prompt loss fraction during counter-Ip injections (similar to 45%) is far larger than during co-Ip injections (similar to 5%) due to the finite orbit width. The lost ions are mainly deposited on the lower divertor or below the midplane since the direction of magnetic drift is vertical down. The orbit types of prompt loss during counter-Ip injections are mainly trapped-lost and ctr-passing lost. To minimize the prompt loss fraction during counter-Ip injections, a reversed Ip configuration (rev-Ip) discharge #94758 was conducted. The result suggests that the beam ion wall load fraction during counter-Ip tangential injection (similar to 3%) is far lower than that in normal Ip configuration (nor-Ip) discharge #94820. It is also found that the confinement of beam ion population in the counter-Ip injection #94758 was greatly improved when compared to #94820. This study can provide unique support for the improvement of beam ion population confinement and for the performance evaluation of the NBI system on EAST and future tokamaks.