[1] 倪木一. 聚变堆燃料循环与氚资源可持续性研究 [D]. 合肥: 中国科学技术大学, 2013.
[2] 谌继明, 王平怀, 金凡亚, 等. ITER 超热负荷第一壁技术 [A]. 中国核科学技术进展报告(第五卷)——中国核学会2017 年学术年会论文集第7 册 [C]. 威海: 中国核学会, 2017.
[3] BARABASH V, AKIBA M, CARDELLA A, et al. Armor and heat sink materials joining technologies development for ITER plasma facing components [J]. Journal of Nuclear Materials, 2000, 283-287: 1248-1252.
[4] SAITO S, FUKAYA K, ISHIYAMA S, et al. Mechanical properties of HIP bonded W and Cu-alloys joint for plasma facing components [J]. Journal of Nuclear Materials, 2002, 307-311: 1542-1546.
[5] 范景莲, 杨树忠, 刘涛, 等. W-Cu 复合材料与Cu 的扩散连接工艺 [J]. 粉末冶金材料科学与工程, 2015, 20(2): 182-186.
[6] DOERING J E, VASSEN R, PINTSUK G, et al. The processing of vacuum plasma-sprayed tungsten-copper composite coatings for high heat flux components [J]. Fusion Engineering and Design, 2003, 66-68(1-4): 259-263.
[7] BOSCARY J, SUZUKI S, NAKAMURA K, et a1. Thermal fatigue tests on CVD-W/Cu divertor mock-ups. [J]. Fusion Engineering and Design, 1998, 39-40: 537-542.
[8] 徐跃. EAST 平板型钨铜面向等离子体部件的制备研究 [D]. 北京: 中国科学院大学, 2014.
[9] SINGH K P, KHIRWADKAR S S, PATEL N, et al. Development of tungsten armored high heat flux plasma facing components for ITER like divertor application [J]. Fusion Engineering and Design, 2019, 146(Part B): 2273-2276.
[10] LITUNOVSKY N, ALEKSEENKO E, MAKHANKOV A, et al. Development of the armoring technique for ITER divertor dome [J]. Fusion Engineering and Design, 2011, 86(9-11): 1749-1752.
[11] 骆瑞雪, 李争显. 不同焊料对Cu/W钎焊接头强度的影响 [J]. 热加工工艺, 2009, 38(9): 109-111.
[12] LI J, YANG J F, CHEN J L. High heat load properties of actively cooled W/CuCrZr mock-ups by diffusion bonding with Ni or Ti interlayer [J]. Fusion Engineering & Design, 2011, 86(12): 2874-2878.
[13] 邹贵生, 杨俊, 吴爱萍, 等. Ti 和Ti/Ni/Ti 复合层连接钨与铜及其合金的界面结合与断裂 [A]. 2002 年中国材料研讨会论文集 [C]. 北京: 中国材料研究学会,2002. 484-490.
[14] NOTO H, YAMADA T, HISHINUMA Y, et al. Development of high strength W/V/Au/ODS-Cu joint using HIP process [J]. Nuclear Materials and Energy, 2016, 9: 411-415.
[15] 王一鸣, 黄攀, 谌继明, 等. W/Fe/CuCrZr 热等静压模块组织及性能分析 [J]. 核聚变与等离子体物理, 2021, 41(2): 7.
[16] BATRA I S, KALE G B, SAHA T K, et al. Diffusion bonding of a Cu-Cr-Zr alloy to stainless steel and tungsten using nickel as an interlayer [J]. Materials Science and Engineering: A, 2004, 369(1-2): 119-123.
[17] 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.
[18] BANG E, CHOI H, KIM H C, et al. Manufacturing and testing of flat type W/Cu/CuCrZr mock-ups by HIP process with PVD coating [J]. Fusion Engineering and Design, 2019, 146(Part A): 603-608.
[19] 刘国辉, 李强, 魏然, 等. 用于核聚变装置的W/Cu 穿管部件的制备与辐照性能研究 [J]. 核聚变与等离子体物理, 2015, 35(1): 75-78.
[20] LI Q, ZHAO S X, SUN Z X, et al. Development and application of W/Cu flat-type plasma facing components at ASIPP [J]. Physica Scripta, 2017, 2017(T170): 014020.
[21] MAKHANKOV A, MAZUL I, SAFRONOV V, et al. Development and optimization of tungsten armour geometry for ITER divertor [C]. Marseille: Proceedings of the 20th Symposium on Fusion Technology, 1998. 267-270.
[22] ODEGARD JR B C, CADDEN C H, WATSON R D, et al. A review of the US joining technologies for plasma facing components in the ITER fusion reactor [J]. Journal of Nuclear Materials, 1998, 258-263(Part 1): 329-334.
[23] PARK J Y, CHOI B K, LEE J S, et al. Fabrication of Be/CuCrZr/SS mock-ups for ITER first wall [J]. Fusion Engineering and Design, 2009, 84(7-11): 1468-1471.
[24] KALIN B A, FEDOTOV V T, SEVRJUKOV O N, et al. Development of rapidly quenched brazing foils to join tungsten alloys with ferritic steel [J]. Journal of Nuclear Materials, 2004, 329-333(Part B): 1544-1548.
|