FW and Blanket Technology Development Progress at SWIP View Full Text


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Article Info

DATE

2021-04-19

AUTHORS

Jiming Chen, Xiaoyu Wang, Pinghuai Wang, Min Xu, Xuru Duan, Kun Wang, Shuqin Wu, Fengchao Zhao, Xiaobo Zhu, Xinghua Wu, Qian Li, Hongbin Liao, Jing Wu, Long Zhang, Yi Zhou, Hongxiang Zhang, Qixiang Cao, Weishan Kang, Baoping Gong, Bo Yang, Bing Zhou, Jialin Li, Fanya Jin, Xingfu Ye, Hui Gao, Jun Wang, Qian Sheng, Pan Huang, Fen Wang, Xiaoping Fan, Hong Yang, Zhen Leng

ABSTRACT

Blanket, including its first wall (FW), is one of the key components in the fusion reactor, which works in the severe condition with the huge high energy neutron irradiation, high heat flux and electromagnetic load. Facing these technical challenges for the blanket and its FW, Southwestern Institute of Physics is engaging in the development of the blanket technology following the proposed China magnetic confinement fusion development strategy. This paper presents the design and R&D progress of the ITER FW and blanket, Chinese helium cooled ceramic breeder test blanket module (HCCB TBM) for ITER and HCCB tritium blanket for China Fusion Engineering Test Reactor (CFETR). The design of the ITER enhanced heat flux FW has been updated to improve manufacturability and to reduce water leak risk. Key technologies have been qualified by high heat flux tests of small mock-ups and full-scale plasma-facing fingers. New assembly technologies are under development. Following the completion of full-scale prototype qualification, the ITER shielding blanket modules are under manufacturing for series production. The preliminary design of HCCB TBM for ITER is under implementation to improve the manufacturability and inspectability based on the fabrication study. Two prototypes of TBM submodule have been fabricated and tested to validate the feasibility of manufacture procedure, which are finally assembling into one semi-prototype of TBM. The preliminary design of HCCB tritium blanket for CFETR has been completed and the R&D has been started, especially for the special technologies different with the ITER blanket and TBM. Meanwhile, the progress of reduced activation ferritic/martensitic steel and function materials for blanket are also presented. More... »

PAGES

10

Identifiers

URI

http://scigraph.springernature.com/pub.10.1007/s10894-021-00301-9

DOI

http://dx.doi.org/10.1007/s10894-021-00301-9

DIMENSIONS

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6 schema:description Blanket, including its first wall (FW), is one of the key components in the fusion reactor, which works in the severe condition with the huge high energy neutron irradiation, high heat flux and electromagnetic load. Facing these technical challenges for the blanket and its FW, Southwestern Institute of Physics is engaging in the development of the blanket technology following the proposed China magnetic confinement fusion development strategy. This paper presents the design and R&D progress of the ITER FW and blanket, Chinese helium cooled ceramic breeder test blanket module (HCCB TBM) for ITER and HCCB tritium blanket for China Fusion Engineering Test Reactor (CFETR). The design of the ITER enhanced heat flux FW has been updated to improve manufacturability and to reduce water leak risk. Key technologies have been qualified by high heat flux tests of small mock-ups and full-scale plasma-facing fingers. New assembly technologies are under development. Following the completion of full-scale prototype qualification, the ITER shielding blanket modules are under manufacturing for series production. The preliminary design of HCCB TBM for ITER is under implementation to improve the manufacturability and inspectability based on the fabrication study. Two prototypes of TBM submodule have been fabricated and tested to validate the feasibility of manufacture procedure, which are finally assembling into one semi-prototype of TBM. The preliminary design of HCCB tritium blanket for CFETR has been completed and the R&D has been started, especially for the special technologies different with the ITER blanket and TBM. Meanwhile, the progress of reduced activation ferritic/martensitic steel and function materials for blanket are also presented.
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13 schema:keywords Ceramic Breeder Test Blanket Module
14 China Fusion Engineering Test Reactor
15 Chinese helium
16 Engineering Test Reactor
17 Fusion Engineering Test Reactor
18 HCCB TBM
19 ITER
20 ITER blanket
21 ITER first wall
22 Institute
23 SWIP
24 Southwestern Institute
25 TBM
26 Test Reactor
27 activation
28 assembly technology
29 blanket
30 blanket module
31 blanket technology
32 challenges
33 completion
34 components
35 conditions
36 design
37 development
38 development progress
39 electromagnetic loads
40 fabrication studies
41 feasibility
42 finger
43 first wall
44 flux
45 flux tests
46 function materials
47 fusion development
48 fusion reactors
49 heat flux
50 heat flux tests
51 helium
52 high heat flux
53 high heat flux tests
54 high-energy neutron irradiation
55 implementation
56 inspectability
57 irradiation
58 key component
59 key technologies
60 leak risk
61 load
62 manufacturability
63 manufacture procedure
64 manufacturing
65 martensitic steel
66 materials
67 module
68 neutron irradiation
69 new assembly technology
70 paper
71 physics
72 preliminary design
73 procedure
74 production
75 progress
76 prototype
77 qualification
78 reactor
79 reduced activation
80 risk
81 series production
82 severe conditions
83 special technology
84 steel
85 strategies
86 study
87 submodules
88 technical challenges
89 technology
90 test
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