A framework for the assessment and control of ITER main chamber heat loads
作者: H. AnandR.A. PittsP.C. De VriesJ.A. SnipesL. KosY. GribovL. ZabeoI. NunesM. Brank
刊名: Nuclear Fusion, 2020, Vol.60 (3)
来源数据库: Institute of Physics Journal
DOI: 10.1088/1741-4326/ab6150
原始语种摘要: A control-oriented approach, based on real-time equilibrium reconstruction, has been developed to monitor power fluxes to ITER plasma-facing components (PFC. The model describes the deposited heat flux as a poloidal flux function with two main input parameters: the power exhausted across the plasma boundary and the scrape-off layer heat flux width. A module containing weighting factors accounts for the real PFC 3D geometry. These factors are obtained using a new sophisticated GUI interface, SMITER, hosting a magnetic field line tracing code permitting the import and appropriate meshing of full PFC CAD descriptions. This new methodology has been used to examine two critically important first wall (FW power loading issues for ITER: the start-up phase at low current and power, but requiring...
全文获取路径: IOP 

  • framework 构架
  • current 
  • control 控制
  • sophisticated 复杂
  • parameters 参数
  • power 功率
  • descriptions 详情
  • chamber 
  • plasma 深绿玉髓
  • reconstruction 复原