EAST was equipped with W-coated divertor plates and dome for the upper divertor, the remaining plasma facing components include the plasma facing components at lower divertor consisted of Carbon materials, at the baffles and main chamber walls consisted of Molybdenum materials. In order to study the control of W impurity on EAST with W divertor by an additional radiation losses, the radiative tungsten divertor with Ar impurity seeding for the control of tungsten impurity is studied by SOLPS-ITER simulation. The computational region includes the core, SOL and private flux region. The real geometry and material of plasma facing components (PFCs) are taken into account. The plasma species in the simulation include $D^0$, $D^{+1}$, $e^{-}$, ${\mathit{He}}^0-{\mathit{He}}^{+2}$, $C^0-C^{+6}$, ${\mathit{Mo}}^0-{\mathit{Mo}}^{+42}$, $W^0-W^{+74}$ and ${\mathit{Ar}}^0-{\mathit{Ar}}^{+18}$. The simulation results show that with the increase of Ar seeding rate at the dome the plasma temperature at the target plates and the concentration of W impurity in the plasma decrease. The simulation plays an important role in the study of radiative tungsten divertor towards the higher heating power and steady state operation.

EAST配备了W涂层的偏滤器板和上偏滤器的圆顶，其余面向等离子体的组件包括位于下部偏滤器的面向等离子体的组件，该下部偏滤器由碳材料制成，在挡板处，主室壁由钼材料组成。为了研究通过附加的辐射损耗控制W偏滤器对EAST上W杂质的控制，通过SOLPS-ITER模拟研究了带有Ar杂质晶种的辐射钨偏滤器以控制W杂质。计算区域包括核心，SOL和私有通量区域。考虑了面向等离子体的组件（PFC）的实际几何形状和材料。模拟中的等离子体种类包括$d^0$， $d^{+\mathrm{1个}}$， ${Ë}^{--}$， ${\mathit{他}}^0--{\mathit{他}}^{+2}$， $C^0--C^{+6}$， ${\mathit{莫}}^0--{\mathit{莫}}^{+42}$， ${\mathrm{w\; ^}}^0--{\mathrm{w\; ^}}^{+74}$ 和 ${\mathit{氩气}}^0--{\mathit{氩气}}^{+\mathrm{18岁}}$。仿真结果表明，随着球顶Ar注入速率的增加，靶板上的等离子体温度和等离子体中W杂质的浓度降低。该仿真在研究辐射钨偏滤器向更高的热功率和稳态工作方面起着重要作用。