Simulation study of the influence of E× B drift on tungsten impurity transport in the scrape-off layer

Tungsten (W) is used as the plasma-facing material in the divertor region of future fusion reactors, such as ITER; however, its concentration in the core plasma must be maintained at an extremely low level. W transport in the scrape-off layer (SOL), which is related to the source of core W contamination, has been extensively studied. In this study, the influence of E × B drift on the transport of W impurity in the SOL is studied via numerical simulations of a model case based on EAST upper single-null configuration with high recycling divertor plasma. W transport is simulated using DIVIMP on the background plasma obtained from scape-off layer plasma simulation-ITER simulation including drifts. The E × B drift of W ions is introduced based on the background electric field. Therefore, both the direct E × B drift effect of W ion and the indirect effect via background plasma on W transport in the SOL are studied. The influence on the flux of W impurities entering confined plasma across the last closed flux surface Γ enter is focused on, which is expected to be proportional to the core W concentration. Results reveal that Γ enter is mainly from the outer (inner) target under a favorable (unfavorable) toroidal field B T and can be increased by more than one order of magnitude compared with the case without drifts; this reflects the significant effect of E × B drift. The effects due to the background plasma and the poloidal and radial E × B drift of W ion, as well as the related mechanisms, are analyzed in detail for three stages of W transport in the SOL: effective sputtering from the target, leakage from the divertor, and entry into the confined plasma.