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NUCLEAR FUSION AND PLASMA PHYSICS ›› 2020, Vol. 40 ›› Issue (2): 109-116.DOI: 10.16568/j.0254-6086.202002003

• Plasma Physics • Previous Articles     Next Articles

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

WANG Jun1, WANG Xiao-yu1, ZHANG Guo-shu2   

  1. (1. Southwestern Institute of Physics, Chengdu 610041; 2. East China University of Technology, Nanchang 330013)
  • Received:2018-11-05 Revised:2019-06-25 Online:2020-06-15 Published:2020-06-15

常规导体托卡马克聚变核科学装置的堆芯参数研究

王 俊1,王晓宇1,张国书2   

  1. (1. 核工业西南物理研究院,成都 610041; 2. 东华理工大学,南昌330013)
  • 作者简介:王俊(1988-),男,湖南省湘潭市人,硕士,助理研究员,从事聚变堆设计。
  • 基金资助:

    国家重点研发计划(2017YFE0300603)

Abstract:

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.

Key words: Tokamak, Normal conductor, Reactor core parameter

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。

关键词: 托卡马克, 常规导体, 堆芯参数

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