|
[1] Ma X, Cheng X, Li X, et al.
Thermal hydraulic design and analysis of updated CFETR water cooled ceramic
breeder blanket [J]. Fusion Eng. Des., 2019, 148: 111317.
[2] Jiang K, Ma X, Cheng X, et al.
Thermal-hydraulic analysis on the whole module of water cooled ceramic breeder
blanket for CFETR [J]. Fusion Eng. Des., 2016, 112: 81−88.
[3] Ling Q, Wang G. A research and
development review of water-cooled breeding blanket for fusion reactors [J].
Annals of Nuclear Energy, 2020, 145: 107541.
[4] Wan Y X, Li J G, Liu Y, et al.
Overview of the present progress and activities on the CFETR [J]. Nucl. Fusion,
2017, 57(10): 102009.
[5] Liu S, Cheng X, Ma X, et al.
Progress on design and related R&D activities for the water-cooled breeder
blanket for CFETR [J]. Theoretical & Applied Mechanics Letters, 2019, 9:
161−172.
[6] Ma X, Cheng X, Liu S, et al.
Thermo-mechanical assessment of the optimized CFETR water cooled ceramic
breeder blanket [J]. Fusion Eng. Des., 2020, 160: 111798.
[7] 王少华, 郭海兵, 马纪敏, 等. 高氚增殖比包层的设计与热工水力分析 [J]. 原子能科学技术, 2017, 51(12): 2125−2131.
[8] 杨士铭, 陶文铨. 传热学(第四版) [M]. 北京: 高等教育出版社, 2006.
[9] Fu H Y, Nagasaka T, Muroga T, et
al. Plastic deformation behavior and bonding strength of an EBW joint between
9Cr-ODS and JLF-1 estimated by symmetric four-point bend tests combined with
FEM analysis [J]. Fusion Eng. Des., 2016, 102: 88–93.
[10] Muroga T, Nagasakaa T, Li Y, et
al. Fabrication and characterization of reference 9Cr and 12Cr-ODS low activation
ferritic/martensitic steels [J]. Fusion Eng. Des., 2014, 89: 1717–1722.
[11] Pintsuk G, Oksiutab Z, Linke J,
et al. High heat flux testing of 12–14Cr ODS ferritic steels [J]. J. Nucl.
Mater., 2010, 396: 20–25.
[12] Lindau R, Möslang A, Rieth M,
et al. ODS-EUROFER -A reduced activation ferritic martensitic ODS-Steels
for application in advanced blanket concepts [Z]. Prague Czech Republic: EUROMAT,
2005.
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