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Progress on design and related R&D activities for the water-cooled breeder blanket for CFETR

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Liu Songlin 1 *   Cheng Xiaoman 1   Ma Xuebin 2   Chen Lei 1   Jiang Kecheng 1,3   Li Xia 1,3   Bao Hui 1,3   Wang Jichao 2   Wang Wanjing 1   Peng Changhong 3   Lu Peng 2   Li Min 1   Huang Kai 1  
文摘 The water-cooled ceramic breeder (WCCB) blanket is one of the blanket candidates for Chinese fusion engineering testing reactor (CFETR) and is being developed at the Institute of Plasma Physics,Chinese Academy of Sciences (ASIPP).This paper reviews design and evolution of the WCCB blanket for CFETR,and presents a new WCCB blanket design according to the latest CFETR core parameters (major and minor radii are R = 7.2 m and a = 2.2 m,respectively) and missions.This new design is expected to satisfy multiple CFETR operation modes of 0.2,0.5,1.0,and 1.5 GW fusion power and achieve tritium self-sufficiency.The feasibility of the updated blanket design is evaluated from the aspects of neutronics and thermo-hydraulics.Furthermore,the research and development (R&D) activities supporting to the WCCB blanket for CFETR are reported,including the design code,the water loop experiments,the pebble bed modeling and experiments,and the components fabrication technology.
来源 Theoretical and Applied Mechanics Letters ,2019,9(3):161-172 【核心库】
DOI 10.1016/j.taml.2019.03.001
关键词 Chinese fusion engineering testing ; reactor ; WCCB blanket ; Research and development
地址

1. Institute of Plasma Physics,Chinese Academy of Sciences, Hefei, 230031  

2. Advanced Energy Research Center,Shenzhen University, Shenzhen, 518060  

3. University of Science and Technology of China, Hefei, 230026

语种 英文
文献类型 研究性论文
ISSN 2095-0349
学科 原子能技术
基金 support of the National Key R&D Program of China ;  国家自然科学基金
文献收藏号 CSCD:6526365

参考文献 共 22 共2页

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引证文献 1

1 Zhou Youhe Mechanics of Tokamak fusion components Theoretical and Applied Mechanics Letters,2019,9(3):145-146
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