Neutronics Analysis of Water-Cooled Ceramic Breeder Blanket for CFETR

被引:1
|
作者
祝庆军 [1 ]
李佳 [2 ]
刘松林 [1 ]
机构
[1] Institute of Plasma Physics, Chinese Academy of Sciences
[2] School of Nuclear Science and Technology, University of Science and Technology of China
基金
中国国家自然科学基金;
关键词
fusion reactor; WCCB blanket; TBR; nuclear heating;
D O I
暂无
中图分类号
TL64 [热核反应堆(聚变堆)];
学科分类号
082701 ;
摘要
In order to investigate the nuclear response to the water-cooled ceramic breeder blanket models for CFETR, a detailed 3D neutronics model with 22.5otorus sector was developed based on the integrated geometry of CFETR, including heterogeneous WCCB blanket models,shield, divertor, vacuum vessel, toroidal and poloidal magnets, and ports. Using the Monte Carlo N-Particle Transport Code MCNP5 and IAEA Fusion Evaluated Nuclear Data Library FENDL2.1,the neutronics analyses were performed. The neutron wall loading, tritium breeding ratio, the nuclear heating, neutron-induced atomic displacement damage, and gas production were determined.The results indicate that the global TBR of no less than 1.2 will be a big challenge for the watercooled ceramic breeder blanket for CFETR.
引用
收藏
页码:775 / 780
页数:6
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