Abstract The modelling studies of SOL-divertor plasmas in EAST tokamak with high heating and driving power have been carried out for the design of W/Cu divertor. The edge plasma code package SOLPS5.0(B2.5-Eirene) and Monte Carlo impurity transport code DIVIMP are used for the modelling. The plasma density at the core-SOL interface Nedge or the separatrix density nsep is varied extensively in order to survey the operation of the divertor, the profiles of the plasma parameters and heat fluxes at the target plates of divertor have been obtained. For nsep=0.937×10191/m3, the heating and driving power Pin=14MW on the device produces the peak heat flux at the outer target plate Qt=15.3MW/m2 with the SN configuration and the traditional divertor (no gas or radiation target). The radiative divertor modelling with Ne puffing and the transport modelling of W impurity from the target plates of divertor are also performed.