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Study on the temperature control mechanism of the tritium breeding blanket for CFETR
Liu, Changle1; Qiu, Yang1,2; Zhang, Jie1; Zhang, Jianzhong3; Li, Lei1; Yao, Damao1; Li, Guoqiang1; Gao, Xiang1; Wu, Songtao1; Wan, Yuanxi1,2
2017-12-01
发表期刊NUCLEAR FUSION
卷号57期号:12
摘要The Chinese fusion engineering testing reactor (CFETR) will demonstrate tritium self-sufficiency using a tritium breeding blanket for the tritium fuel cycle. The temperature control mechanism (TCM) involves the tritium production of the breeding blanket and has an impact on tritium self-sufficiency. In this letter, the CFETR tritium target is addressed according to its missions. TCM research on the neutronics and thermal hydraulics issues for the CFETR blanket is presented. The key concerns regarding the blanket design for tritium production under temperature field control are depicted. A systematic theory on the TCM is established based on a multiplier blanket model. In particular, a closed-loop method is developed for the mechanism with universal function solutions, which is employed in the CFETR blanket design activity for tritium production. A tritium accumulation phenomenon is found close to the coolant in the blanket interior, which has a very important impact on current blanket concepts using water coolant inside the blanket. In addition, an optimal tritium breeding ratio (TBR) method based on the TCM is proposed, combined with thermal hydraulics and finite element technology. Meanwhile, the energy gain factor is adopted to estimate neutron heat deposition, which is a key parameter relating to the blanket TBR calculations, considering the structural factors. This work will benefit breeding blanket engineering for the CFETR reactor in the future.
文章类型Article
关键词Temperature Control Mechanism Breeding Blanket Tritium Self-sufficiency Tritium Breeding Ratio Cfetr
WOS标题词Science & Technology ; Physical Sciences
资助者National Magnetic Confinement Fusion Program of China(2014GB110000) ; National Magnetic Confinement Fusion Program of China(2014GB110000) ; National Magnetic Confinement Fusion Program of China(2014GB110000) ; National Magnetic Confinement Fusion Program of China(2014GB110000)
DOI10.1088/1741-4326/aa7f3e
关键词[WOS]SUBCRITICAL WATER CONDITION ; HYDRAULIC ANALYSIS ; FUSION-REACTOR ; DESIGN ; DEMO ; FLOW
收录类别SCI
语种英语
资助者National Magnetic Confinement Fusion Program of China(2014GB110000) ; National Magnetic Confinement Fusion Program of China(2014GB110000) ; National Magnetic Confinement Fusion Program of China(2014GB110000) ; National Magnetic Confinement Fusion Program of China(2014GB110000)
WOS研究方向Physics
WOS类目Physics, Fluids & Plasmas
WOS记录号WOS:000412386200002
引用统计
文献类型期刊论文
条目标识符http://ir.hfcas.ac.cn:8080/handle/334002/33703
专题中科院等离子体物理研究所
作者单位1.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China
2.Univ Sci & Technol China, Hefei 230026, Anhui, Peoples R China
3.Hefei Univ Technol, Hefei 230026, Anhui, Peoples R China
推荐引用方式
GB/T 7714
Liu, Changle,Qiu, Yang,Zhang, Jie,et al. Study on the temperature control mechanism of the tritium breeding blanket for CFETR[J]. NUCLEAR FUSION,2017,57(12).
APA Liu, Changle.,Qiu, Yang.,Zhang, Jie.,Zhang, Jianzhong.,Li, Lei.,...&Wan, Yuanxi.(2017).Study on the temperature control mechanism of the tritium breeding blanket for CFETR.NUCLEAR FUSION,57(12).
MLA Liu, Changle,et al."Study on the temperature control mechanism of the tritium breeding blanket for CFETR".NUCLEAR FUSION 57.12(2017).
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