[1] Wu S T, EAST team. An overview of the EAST project[J]. Fusion Engineering and Design, 2007, 82(5-14):463-471.
[2] Song Y T, Zhou X L, Gong X Z, et al. Realization of thousand-second improved confinement plasma with super I-mode in tokamak EAST [J]. Science Advances,2023, 9(1): eabq5273.
[3] Hu C D, Xie Y L, Xie Y H, et al. Overview of development status for EAST-NBI system [J]. Plasma Science and Technology, 2015, 17(10): 817-825.
[4] Hu C D. Conceptual design of neutral beam injection system for EAST [J]. Plasma Science and Technology,2012, 14(6): 567-572.
[5] 胡纯栋, 张为堂, 许永建, 等. EAST 中性束穿透损失分析 [J]. 强激光与粒子束, 2015, 27(12): 268-272.
[6] Luo G N, Liu G H, Li Q, et al. Overview of decade-long development of plasma-facing components at ASIPP [J].Nuclear Fusion, 2017, 57(6): 065001.
[7] Wang J F, Li Y Y, Wu B, et al. Numerical and experimental evaluation of shine-through loss and beam heating due to neutral beam injection on EAST [J].Chinese Physics Letters, 2021, 38(5): 055203.
[8] Wu B, Hao B L, White R, et al. Calculation of prompt loss and toroidal field ripple loss under neutral beam injection on EAST [J]. Plasma Physics and Controlled Fusion, 2016, 59(2): 025004.
[9] Yao D M, Bao L M, Li J G, et al. Design, analysis and R&D of the EAST in-vessel components [J]. Plasma Science and Technology, 2008, 10(3): 367.
[10] Song Y T, Peng X B, Xie H, et al. Plasma facing components of EAST [J]. Fusion Engineering and Design,2010, 85(10-12): 2323-2327.
[11] Eto M, Ishiyama S, Ugachi H, et al. Mechanical properties of neutron-irradiated carbon-carbon composites for plasma facing components [J]. Journal of nuclear materials, 1994,212-215(Part B): 1223-1227.
[12] 刘严伟. EAST 装置面向等离子体部件碳基材料钎焊工艺研究 [D]. 合肥: 中国科学技术大学, 2019.
[13] LI L, HAN L, ZIP F, et al. Conceptual design and heat transfer performance of a flat-tile water-cooled divertor target [J]. Plasma Science and Technology, 2021, 23(9):194-205.
[14] 庄清, 明廷凤, 余耀伟, 等. 基于 EAST 装置量热系统的第一壁热负荷实验研究 [J]. 核聚变与等离子体物理, 2020, 40(3): 222-226.
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