A divertor plasma configuration design method for tokamaks  

作　　者：郭勇 肖炳甲 刘磊 杨飞 汪悦航 仇庆来 

机构地区：[1]Institute of Plasma Physics, Chinese Academy of Science [2]School of Nuclear Science and Technology, University of Science and Technology of China [3]Department of Computer Science, Anhui Medical University [4]CAS Key Laboratory of Basic Plasma Physics and Department of Modern Physics, University of Science and Technology of China

出　　处：《Chinese Physics B》2016年第11期378-386,共9页中国物理B（英文版）

基　　金：Project supported by the National Magnetic Confinement Fusion Research Program of China(Grant Nos.2014GB103000 and 2014GB110003);the National Natural Science Foundation of China(Grant Nos.11305216,11305209,and 11375191);External Cooperation Program of BIC,Chinese Academy of Sciences(Grant No.GJHZ201303)

摘　　要：The efficient and safe operation of large fusion devices strongly relies on the plasma configuration inside the vacuum chamber.It is important to construct the proper plasma equilibrium with a desired plasma configuration.In order to construct the target configuration,a shape constraint module has been developed in the tokamak simulation code（TSC）,which controls the poloidal flux and the magnetic field at several defined control points.It is used to construct the double null,lower single null,and quasi-snowflake configurations for the required target shape and calculate the required PF coils current.The flexibility and practicability of this method have been verified by the simulated results.The efficient and safe operation of large fusion devices strongly relies on the plasma configuration inside the vacuum chamber.It is important to construct the proper plasma equilibrium with a desired plasma configuration.In order to construct the target configuration,a shape constraint module has been developed in the tokamak simulation code（TSC）,which controls the poloidal flux and the magnetic field at several defined control points.It is used to construct the double null,lower single null,and quasi-snowflake configurations for the required target shape and calculate the required PF coils current.The flexibility and practicability of this method have been verified by the simulated results.

关 键 词：constraint verified desired reconstructed iteration flexibility radial offset consuming corrected 

分 类 号：O53[理学—等离子体物理] TL631.24[理学—物理]