[1] Ma X, Cheng X, Liu S, et al. Thermo-mechanical
assessment of the optimized CFETR water cooled
ceramic breeder blanket [J]. Fusion Engineering and
Design, 2020, 160: 111798.
[2] Pinna T, Carloni D, Carpignano A, et al. Identification of
accident sequences for the DEMO plant [J]. Fusion
Engineering and Design, 2017, 124: 1277-1280.
[3] Cheng X, Ma X, Wang W, et al. Primary heat transfer
system design of the WCCB blanket for multiple
operation modes of CFETR [J]. Fusion Engineering and
Design, 2020, 153: 111489.
[4] Cheng X, Ma X, Lu P, et al. Thermal dynamic analyses of
the primary heat transfer system for the WCCB blanket
of CFETR [J]. Fusion Engineering and Design, 2020, 161:
112067.
[5] Jin X. BB LOCA analysis for the reference design of the
EU DEMO HCPB blanket concept [J]. Fusion
Engineering and Design, 2018, 136(PT.B): 958-963.
[6] Cheng X, Ma X, Chen Y, et al. Preliminary thermal
hydraulic safety analysis of water-cooled ceramic breeder
blanket for CFETR [J]. Journal of Nuclear Science and
Technology, 2016, 53(11): 1673-1680.
[7] 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 Engineering and
Design, 2016, 112: 81-88.
[8] Abdou M, Morley N B, Smolentsev S, et al. Blanket/first
wall challenges and required R&D on the pathway to
DEMO [J]. Fusion Engineering and Design, 2015, 100:
2-43.
[9] Ma X, Cheng X, Li X, et al. Thermal hydraulic design
and analysis of updated CFETR water cooled ceramic
breeder blanket [J]. Fusion Engineering and Design, 2019,
148: 111317.
[10] Iseli M. Safety guidelines for test blanket systems (V3.1)
[R]. ITER_D_338HVX, 2011.
[11] Topilski M. Safety analysis date list (V5.2.6) [R].
ITER_D_2EH97G, 2008.
[12] 杨庆喜. CFETR 装置主机外杜瓦系统设计 [R]. 廊坊:
CFETR 集成工程设计年会暨聚变堆设计研讨会, 2020.
[13] Zhuang G, Li G, Li J, et al. Progress of the CFETR design
[J]. Nucl. Fusion, 2019, 59: 112010.
[14] Haertl T, Bachmann C, Diegele E, et al. Rationale for the
selection of the operating temperature of the DEMO
vacuum vessel [J]. Fusion Engineering and Design, 2019,
146(PT.A): 1096-1099.
[15] Nakamura M, Watanabe K, Tobita K, et al.
Thermohydraulic analysis of accident scenarios of a
fusion demo reactor based on water-cooled ceramic
breeder blanket: analysis of LOCAs and LOVA [J]. IEEE
Transactions on Plasma Science, 2016, 44(9):
1689-1699.
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