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

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【作者】 Songlin LiuXiaoman ChengXuebin MaLei ChenKecheng JiangXia LiHui BaoJichao WangWanjing WangChanghong PengPeng LuMin LiKai Huang

【Author】 Songlin Liu;Xiaoman Cheng;Xuebin Ma;Lei Chen;Kecheng Jiang;Xia Li;Hui Bao;Jichao Wang;Wanjing Wang;Changhong Peng;Peng Lu;Min Li;Kai Huang;Institute of Plasma Physics, Chinese Academy of Sciences;Advanced Energy Research Center, Shenzhen University;University of Science and Technology of China;

【通讯作者】 Songlin Liu;

【机构】 Institute of Plasma Physics, Chinese Academy of SciencesAdvanced Energy Research Center, Shenzhen UniversityUniversity of Science and Technology of China

【摘要】 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.

【Abstract】 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.

【基金】 the financial support of the National Key R&D Program of China(Grants2017YFE0300503 and 2017YFE0300604);the National Natural Science Foundation of China(Grant 11775256)
  • 【文献出处】 Theoretical & Applied Mechanics Letters ,力学快报(英文) , 编辑部邮箱 ,2019年03期
  • 【分类号】TL411
  • 【被引频次】3
  • 【下载频次】21
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