摘要
基于中国聚变工程实验堆(CFETR)水冷陶瓷增殖剂(WCCB)三维中子学模型,应用蒙特卡罗输运程序MCNP5和IAEA聚变评价核数据库FENDL2.1,完成了WCCB中子学性能分析。研究了在200MW、500MW、1.0GW、1.5GW聚变功率下中子壁载荷(NWL)、氚增殖率(TBR)、核热沉积以及包层材料的辐照损伤。结果显示,目前WCCB包层核分析结果满足CFETR设计要求。
Based on a three-dimensional water-cooled ceramic breeder(WCCB)blanket model for the China Fusion Engineering Test Reactor(CFETR),neutronics analyses are performed by utilizing the MCNP5 code and the IAEA Fusion Evaluated Nuclear Data Library FENDL2.1.The results include neutron wall loading(NWL),tritium breeding ratio(TBR),nuclear heating power and radiation damage under 200 MW,500 MW,1.0GW,1.5 GW fusion power.The results show that the neutronics analyses of WCCB meet the design requirements of CFETR.
作者
李夏
马学斌
卢棚
郑俞
徐坤
刘松林
LI Xia;MA Xue-bin;LU Peng;ZHENG Yu;XU Kun;LIU Song-lin(Institute of Plasma Physics,Chinese Academy of Sciences,Hefei 230031;University of Science and Technology of China,Hefei 230026;Shenzhen University,Shenzhen 518060)
出处
《核聚变与等离子体物理》
CAS
CSCD
北大核心
2020年第3期275-282,共8页
Nuclear Fusion and Plasma Physics
基金
国家重点研发计划(2017YFE0300503)。
