托卡马克极向场线圈的优化方法  

Equilibrium optimization code opeq and results of applying it to HT-7U

作　　者：查学军 朱思铮[1] 虞清泉 

机构地区：[1]中国科学院等离子体物理研究所,合肥1126信箱230031

出　　处：《物理学报》2003年第2期428-433,共6页Acta Physica Sinica

摘　　要：托卡马克等离子体的三角形变和拉长比对约束和磁流体稳定性有很强的影响 ,因此在托卡马克装置极向场设计中 ,在基于物理和工程考虑所预先选定的等离子体平衡位形几何参数下 ,如何优化确定外部极向场线圈位置和电流 ,是一个具有重要实际意义的研究课题 .为优化确定托卡马克极向场线圈 ,给出了一个有效的多变量平衡优化方法 ,能以事先规定的等离子体平衡位形的一些几何参数为目标函数 ,优化确定极向场线圈位置和电流 .并应用它于HT 7U平衡位形计算 ,得到了所需的结果 .The plasma equilibrium configuration has a strong impact on the confinement and MHD stability in tokamaks. For designing a tokamak device, it is an important issue to determine the sites and currents of poloidal coils which have some constraint conditions from physics and engineering with a prescribed equilibrium shape of the plasma. In this paper, an effective method based on multi-variables equilibrium optimization is given. The method can optimize poloidal coils when the previously prescribed plasma parameters are treated as an object function. We apply it to HT-7U equilibrium calculation, and abtain good results.

关 键 词：等离子体平衡 极向场线圈 优化 托卡马克装置 

分 类 号：TL631.24[核科学技术—核技术及应用]