常规导体托卡马克聚变核科学装置的堆芯参数研究  

Reactor core parameter study of fusion nuclear science facility based on normal conductor Tokamak

作　　者：王俊[1] 王晓宇[1] 张国书 WANG Jun;WANG Xiao-yu;ZHANG Guo-shu(Southwestern Institute of Physics,Chengdu 610041;East China University of Technology,Nanchang 330013)

机构地区：[1]核工业西南物理研究院,成都610041 [2]东华理工大学,南昌330013

出　　处：《核聚变与等离子体物理》2020年第2期109-116,共8页Nuclear Fusion and Plasma Physics

基　　金：国家重点研发计划(2017YFE0300603)。

摘　　要：采用自主研发的零维系统程序ZERO-CODE,对基于铜线圈托卡马克概念的聚变装置开展了堆芯关键参数的设计。根据中子峰值壁面负载及相关物理、工程要求,确定了一组具有最优造价的堆芯参数。Core parameters of the fusion facility based on the concept of copper coil tokamak are designed with self-developed zero dimensional system code, ZEROCODE. Based on the neutron peak wall load and related physical and engineering requirements, a set of core parameters with optimal cost is determined for the fusion facility.

关 键 词：托卡马克 常规导体 堆芯参数 

分 类 号：TL622[核科学技术—核技术及应用]