The transport and radiation loss of tungsten impurities in core plasma for the CFEDR conventional H-mode scenario

Impurity transport in the China Fusion Engineering Demo Reactor (CFEDR) conventional H-mode scenario is investigated self-consistently with physics-based core transport. A workflow composed of integrated modeling of the main plasma, the impurity transport calculation module and the radial distribution calculation module has been established. The simulation yields density profiles of tungsten impurities in different ionization states, as well as the total density profiles and total radiation losses of tungsten. The simulation results demonstrate that the total radiation losses from tungsten, with the edge impurity concentration estimated from first-wall erosion, are not a concern for H–L back transition. Under the dominance of turbulent transport, the simulation results reveal a flat radial profile for the total tungsten density. This finding indicates a substantial correlation between the total radiation losses from tungsten impurities and the transport magnitudes in the pedestal and the scrape-off layer regions, as well as the rate of the neutral tungsten particle source outside the pedestal.