Double-null divertor configuration discharge and disruptive heat flux simulation using TSC on EAST  

作　　者：Bo SHI Jinhong YANG Cheng YANG Desheng CHENG Hui WANG Hui ZHANG Haifei DENG Junli QI Xianzu GONG Weihua WANG 史博;杨锦宏;杨程;程德胜;王辉;张辉;邓海飞;祁俊力;龚先祖;汪卫华(Institute of Plasma Physics, Hefei Institutes of Physical Sciences, Chinese Academy of Sciences;Science Island Branch of Graduate School, University of Science and Technology of China;Institute of Applied Physics, Army Officer Academy)

机构地区：[1]Institute of Plasma Physics,Hefei Institutes of Physical Sciences,Chinese Academy of Sciences,Hefei 230031,People＇s Republic of China [2]Science Island Branch of Graduate School,University of Science and Technology of China,Hefei 230031,People＇s Republic of China [3]Institute of Applied Physics,Army Officer Academy,Hefei 230031,People＇s Republic of China

出　　处：《Plasma Science and Technology》2018年第7期35-40,共6页等离子体科学和技术（英文版）

基　　金：supported by National Natural Science Foundation of China(Grant Nos.11505290,51576208 and11575239);the National Magnetic Confinement Fusion Science Program of China(No.2015GB102004)

摘　　要：The tokamak simulation code （TSC） is employed to simulate the complete evolution of a disruptive discharge in the experimental advanced superconducting tokamak. The multiplication factor of the anomalous transport coefficient was adjusted to model the major disruptive discharge with double-null divertor configuration based on shot 61 916. The real-time feed-back control system for the plasma displacement was employed. Modeling results of the evolution of the poloidal field coil currents, the plasma current, the major radius, the plasma configuration all show agreement with experimental measurements. Results from the simulation show that during disruption, heat flux about 8 MW m-2 flows to the upper divertor target plate and about 6 MW m-2 flows to the lower divertor target plate. Computations predict that different amounts of heat fluxes on the divertor target plate could result by adjusting the multiplication factor of the anomalous transport coefficient. This shows that TSC has high flexibility and predictability.The tokamak simulation code （TSC） is employed to simulate the complete evolution of a disruptive discharge in the experimental advanced superconducting tokamak. The multiplication factor of the anomalous transport coefficient was adjusted to model the major disruptive discharge with double-null divertor configuration based on shot 61 916. The real-time feed-back control system for the plasma displacement was employed. Modeling results of the evolution of the poloidal field coil currents, the plasma current, the major radius, the plasma configuration all show agreement with experimental measurements. Results from the simulation show that during disruption, heat flux about 8 MW m-2 flows to the upper divertor target plate and about 6 MW m-2 flows to the lower divertor target plate. Computations predict that different amounts of heat fluxes on the divertor target plate could result by adjusting the multiplication factor of the anomalous transport coefficient. This shows that TSC has high flexibility and predictability.

关 键 词：TSC EAST disruptive discharge heat flux 

分 类 号：TP273[自动化与计算机技术—检测技术与自动化装置] TQ320.662[自动化与计算机技术—控制科学与工程]