Experimental Advanced Superconducting Tokamak 先进超导托卡马克实验装置 ; 超导托卡马克实验装置 ; 东方超环
Full Superconducting Tokamak 全超导托卡马克装置 ; 托卡马克装置
EAST superconducting Tokamak EAST超导托卡马克
experiment advanced superconducting Tokamak 超导Tokamak实验装置
superconducting tokamak device 超导托卡马克装置
Fully Superconducting Tokamak EAST 全超导托卡马克EAST
Tokamak superconducting magnet coil 托卡马克超导磁体
The plasma shape equilibrium and fitting code (EFIT) is the basis and important element of experimental advanced superconducting tokamak (EAST) superconducting Tokamak control system. The physics concept of EFIT code applied in Tokamak is described.
等离子体位形平衡和反演算法是EAST超导托卡马克控制系统的基础和重要组成部分。
参考来源 - EAST超导托卡马克等离子体位形平衡和反演算法 in C·2,447,543篇论文数据，部分数据来源于NoteExpress
The thermal shield (TS) is a main part of EAST superconducting Tokamak.
冷屏是EAST超导托卡马克核聚变实验装置的重要部件之一。
So boronization can provide a fine first wall condition for HT7 superconducting tokamak stable operation.
由此证实了硼化为HT - 7稳态运行提供了良好的壁条件。
The application of distribute control system (DCS) in poloidal field power supply of HT-7 superconducting tokamak device is described.
介绍了集散控制系统在世界第四大超导托卡马克装置极向场控制系统中的应用。
应用推荐