A simple and fast method to calculate the coil currents and the external poloidal flux and magnetic field for fixed boundary equilibria  

作　　者：Ricardo FARENGO Pablo L GARCÍA-MARTÍNEZ Hugo E FERRARI 

机构地区：[1]Centro Atómico Bariloche,Comisión Nacional de Energía Atómica,Bariloche 8400,Argentina [2]Instituto Balseiro,Universidad Nacional de Cuyo,Bariloche 8400,Argentina [3]CONICET CCT-Patagonia Norte,Bariloche 8400,Argentina

出　　处：《Plasma Science and Technology》2024年第11期65-70,共6页等离子体科学和技术（英文版）

基　　金：supported by the Comisión Nacional de Energía Atómica, CNEA (Controlled Nuclear Fusion Program);CONICET (Grant PIP 11220200101929CO)。

摘　　要：A simple and fast method to calculate the coil currents and the external poloidal flux and magnetic field consistent with a given internal magnetohydrodynamic(MHD) equilibrium and coil geometry is presented. The constrained optimization technique employed allows to fix the exact position of the X-points. The external poloidal flux and field are calculated using Green's functions expressed in terms of elliptic integrals that are calculated using a fast and accurate routine.The calculation can be limited to the region between the plasma and the device wall. An example for a double null configuration is presented.

关 键 词：MHD equilibrium Green's functions TOKAMAK 

分 类 号：TL612[核科学技术—核技术及应用]