Superconducting Magnet Systems in Tokamak Engineering and Optimization
Superconducting Magnet Systems in Tokamak Engineering and Optimization
复制标题
托卡马克工程和优化中的超导磁体系统
DOI：
10.1109/tasc.2016.2522652
复制
发表时间：
2016
影响因子：
1.8
通讯作者：
L. Reccia
中科院分区：
文献类型：
--
作者：
A. Portone;G. D'Amico;L. Reccia
本文的目的是研究超导托卡马克中等离子体整形和磁体系统之间的相互作用。特别是，我们研究了超导环向场(TF)线圈系统的布局随等离子体延伸率(κXP)和长径比(A)的变化而优化。通过排除血管内控制线圈的使用，我们将等离子体延伸率作为纵横比的函数最大化，以确保等离子体在垂直位移事件下的安全运行。在这方面，来自托卡马克运行经验的设计标准以及其他设计被用作指导。然后对超导磁体系统的布局进行了优化，以满足等离子体轴上基准磁场的关键要求、等离子体边界处的最大磁场纹波、伏秒可用性和等离子体成形，同时满足导体温度裕度、磁场线圈中央穹顶的峰值应力和中心螺线管的环向应力的约束。
The aim of this paper is to study the interplay between plasma shaping and magnet systems in superconducting tokamaks. In particular, we study the optimization of the layout of the superconducting toroidal field (TF) coil system as a function of plasma elongation (κxp) and aspect ratio (A). By excluding the use of in-vessel control coils, we proceed by maximizing plasma elongation as a function of the aspect ratio to keep plasma operation safe with respect to vertical displacement events. In this respect, design criteria coming from tokamak operational experience as well as other designs are used as guidance. The layout of the superconducting magnet systems is then optimized to meet the key requirements of reference TF on the plasma axis and maximum TF ripple at the plasma boundary, volt-seconds availability, and plasma shaping while satisfying the constraints of conductor temperature margins, peak stresses in the TF coil central vault, and hoop stress in the central solenoid.