Tungsten (W) impurity eroded from the divertor target can degrade the confinement performance of future fusion reactors. The mechanism of the effect of E × B drift on the W transport in the scrape‐off layer (SOL) was investigated with a fixed cross‐field anomalous particle diffusion coefficient for W ions ( D ⊥,W ) of 1 m 2 s −1 in our previous simulation work, which indicates that the W flux entering the confined region ( Γ enter ) and mean W concentration in the confined region () can be increased by more than one order of magnitude by drifts. In this work, the influence of the cross‐field anomalous diffusion on the W transport in the SOL is further investigated. The basic flow pattern of the W ion flux ( Γ W ) keeps when D ⊥,W varying from 0.5 to 3 m 2 s −1 , and Γ enter mainly comes from the hotter divertor region. Results show that D ⊥,W value affects the W leakage from divertor region and entry into confined region. Therefore, Γ enter and both decrease with increasing D ⊥,W . Mechanisms for cases w/wo drifts are compared.
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Guo et al. (2024) studied this question.
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