HT-7U托卡马克核聚变装置中纵场超导磁体系统的设计  

Design of toroidal field magnet system for superconducting tokamak HT-7U

作　　者：高大军[1] 陈文革[2] 翁佩德[2] 

机构地区：[1]合肥工业大学仪器仪表学院,安徽合肥230009 [2]中国科学院等离子体物理研究所,安徽合肥230031

出　　处：《合肥工业大学学报（自然科学版）》2004年第2期118-122,共5页Journal of Hefei University of Technology：Natural Science

基　　金：九五"国家重大科学工程资助项目([1998]1303号)

摘　　要：HT-7U核聚变实验装置是"九五"国家重大科学工程项目,它是一个具有非圆截面的全超导托卡马克装置,是用于研究先进的托卡马克运行模式来获得准稳态的、极长的长脉冲等离子体,并可实现全电流下的双零高β和单零等离子体的运行实验。整个装置包括装置主机以及低温、真空、电源及控制、数据采集和处理、波加热、波驱动电流、诊断与公共基础设施等重要子系统,其中装置主机是由超导纵场磁体系统、超导极向场磁体系统、真空室及其内部部件、内外冷屏和外真空杜瓦5大部件组成。文章主要介绍了HT-7U纵场超导磁体系统结构与超导管状电缆CICC(Cable-in-ConduitConductor)的设计以及该磁体系统的各种力学分析等。The HT-7U superconducting tokamak with noncircular cross-section is one of the great scientific projects of the Ninth-Five-Year-Plan national scheme. The main object of the project is to build a full superconducting tokamak and study advanced tokamak operational modes so as to achieve steady state and long pulse operation and the operation of double-null and high-beta plasma as well as single-null plasma at full current. This system consists of a tokamak device and some important subsystems concerning cryogenics, vacuum, power supply and control, data acquisition and disposal, wave heating, lower hybrid current drive, diagnoses and public works. The tokamak device includes the superconducting toroidal field and poloidal field (PF) magnets, the vacuum vessel, the thermal shields and cryostat. This paper deals with the design and stress analysis of toroidal field superconducting magnet system and the design of cable-in-conduit conductor (CICC), which is used in the TF coils.

关 键 词：托卡马克 核聚变装置 纵场超导磁体系统 等离子体 

分 类 号：TL622[核科学技术—核技术及应用]