[1] Raffray A R, Calcagno B, Chappuls P, et al. The ITER blanket system design challenge [J]. Nucl. Fusion, 2014,54: 033004.
[2] Barabash V R, Kalinin G M, et al. Specification of CuCrZr alloy properties after various thermo-mechanical treatments and design allowables including neutron irradiation effects [J]. J. Nucl. Mater., 2011, 417(1−3):904−907.
[3] 王锡胜, 张鹏程, 鲜晓斌, 等. Be/CuCrZ 热等静压扩散连接界面特性 [J]. 稀有金属材料与工程, 2008, 37(12):2161−2164.
[4] Lee D W, Bae Y D, Kim S K, et al. High heat flux test with HIP bonded Be/Cu/SS mock-ups for the ITER first wall [J]. Fusion Eng. Des., 2009, 84(7−11): 1160−1163.
[5] Dell G, Orco, Lorenzetto P, et al. Progress on fatigue characterization of ITER primary first wall mock-ups [J].Fusion Eng. Des., 2003, 66: 311−316.
[6] Odegard B C, Cadden C H, Yang N Y C, et al. Failure analysis of beryllium tile assemblies following high heat flux testing for the ITER program [J]. Fusion Eng. Des.,2000, 49−50: 309−316.
[7] 刘丹华, 王平怀, 李前, 等. ITER 第一壁模块Be/Cu 连接界面的热疲劳损伤分析 [J]. 核聚变与等离子体物理, 2017, 37(2): 188−193. |