[1] 邱励俭. 聚变能及其应用 [M]. 北京: 科学出版社,2008. 163.
[2] Jardin S, Menard J, Kessel C, et al. Description of Jsolver V1.3 input file INEQU [R]. Princeton: PPPL, 1999.
[3] Chu D L, Wu B, Wu Y C, et al. Preliminary analysis of advanced equilibrium configuration for the fusion-driven subcritical system [J]. Plasma Science and Technology,2003, 5(6): 2085−2092.
[4] Wu Bin. Introduction of fusion driven subcritical system plasma design [J]. Fusion Engineering and Design, 2003,66−68: 181−186.
[5] 吴斌. HT-7U 超导托卡马克装置的放电模拟研究 [D].合肥: 中国科学院等离子体物理研究所, 2002.
[6] Wan B N, Li J G, Wu Y C, et al. Progress in technology and experiment of superconducting tokamaks in ASIPP[J]. Fusion Engineering and Design, 2010, 85: 1048–1053.
[7] Tobita K, Nishio S, Sato M, et al. Concept of compact low aspect ratio demo rector, slim CS [A]. 21th IAEA Fusion Energy Conference [C]. Chengdu, 2006. 16−22.
[8] 陈美霞, 吴斌, 周晓林, 等. 紧凑型聚变裂变混合堆参数优化及数值模拟 [J]. 核聚变与等离子体物理, 2008,28(3): 247−251.
[9] Nishio S, Ushigusa K. Conceptual design of advanced steady-state tokamak reactor [A]. 18th IAEA Fusion Energy Conference[C]. Sorrento, Italy, 2000. 4−10.
[10] Zohm H, Angioni C, Fable E, et al. On the physics guidelines for a tokamak DEMO [J]. Nucl. Fusion, 2013,53(7): 3019−3025.
[11] Simonin A, H de Esch, Doceul L, et al. Conceptual design of a high-voltage compact bushing for application to future N-NBI systems of fusion reactors [J]. Fusion Engineering and Design, 2013, 88: 1–7.
[12] ITER EDA documentation. Summary ITER final design report [R]. GA0FDR2 01−12−19 W0.1, 2001.
[13] John Wesson. Tokamaks. [M] New York: Oxford University Press, Inc., 1997. 166−168.
[14] 张一鸣, 曾丽萍, 沈欣媛, 等. ITER 计划与聚变能发展战略[J]. 核聚变与等离子体物理, 2013, 33(4): 359−365.
[15] Allen H Boozer. Stellarators and the path from ITER to DEMO [J] .Plasma Phys. Contr. Fusion, 2008, 50(12):4005−4022.
[16] 陈美霞, 刘成岳, 吴斌. 紧凑型聚变裂变混合堆先进运行模式的数值模拟 [J]. 核聚变与等离子体物理,2012, 32(4): 323−327.
[17] 李昊, 吴斌, 王进芳, 等. EAST 4MW 中性束注入放电模拟研究 [J]. 核聚变与等离子体物理, 2014, 34(1): 57−62.