Design of the Water-Cooled Ceramic Breeder blanket for CFETR

被引:17
|
作者
Liu, Songlin [1 ]
Chen, Lei [1 ]
Ma, Xuebin [2 ]
Cheng, Xiaoman [3 ]
Lu, Peng [3 ]
Lei, Mingzhun [1 ]
Jiang, Kecheng [1 ]
Zhao, Xueli [1 ,4 ]
Wang, Xujia [5 ]
Huang, Kai [1 ]
Wu, Qiuran [1 ,4 ]
Wang, Wenjia [1 ,4 ]
Yu, Yi [1 ,4 ]
Ling, Qixin [1 ,4 ]
机构
[1] Chinese Acad Sci, Inst Plasma Phys, Hefei Inst Phys Sci, Hefei 230031, Peoples R China
[2] Shenzhen Univ, Adv Energy Res Ctr, Shenzhen 518060, Peoples R China
[3] Hefei Comprehens Natl Sci Ctr, Inst Energy, Hefei 230000, Anhui, Peoples R China
[4] Univ Sci & Technol China, Hefei 230026, Peoples R China
[5] Shanghai Nucl Engn Res & Design Inst Co Ltd, Shanghai 200233, Peoples R China
基金
国家重点研发计划; 中国国家自然科学基金;
关键词
CFETR; WCCB blanket; Performance analysis; Primary Heat Transfer System; Divertor blanket; RESEARCH-AND-DEVELOPMENT; CONCEPTUAL DESIGN; WCCB BLANKET; PROGRESS; SYSTEM;
D O I
10.1016/j.fusengdes.2022.113059
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The Water-Cooled Ceramic Breeder (WCCB) blanket is one of the blanket candidates for the Chinese Fusion Engineering Testing Reactor (CFETR). In the current version, the WCCB blanket was designed to fulfill the requirements of operating in multiple fusion power modes (200 MW, 500 MW, 1 GW and 1.5 GW) of CFETR while satisfying the tritium self-sufficiency. Structural designs were carried out for typical inboard and outboard modules. Adequate neutron shielding capability and acceptable thermo-mechanical performance were achieved according to the analyses. The global Tritium Breeding Ratio (TBR) was 1.165 with full blanket coverage. It reduced to 1.052 considering the ports occupied by auxiliary heating systems and diagnostic systems. Eventually, the TBR increased to 1.123 by applying the approach of divertor blanket. Besides, two independent cooling systems were applied to adapt to different fusion powers. One cooling system provided coolant for the first wall, the other for breeder zones. The corresponding Primary Heat Transfer System (PHTS) was designed and main operation parameters were obtained under the fusion power of 200 MW~1.5 GW.
引用
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页数:8
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