Abstract: The divertor is the core component of controlled nuclear fusion device. The plasma facing materials of the divertor must be able to withstand the combined effects of high-temperature plasma-generated strong heat flux, particle flux and neutron irradiation. These effects may cause material damage and impurity generation, resulting in energy loss of the plasma and a decrease in confinement efficiency. Meanwhile, the recirculation of fuel particles that remain on the plasma first wall also directly affects the control of plasma density. The damage failure behaviors of plasma facing meterial under service conditions of high heat load, plasma irradiation and neutron irradiation are reviewed. The main candidate of plasma facing materials, such as carbon-based materials, beryllium metal and tungsten-based materials are deseribed. The strengthening strategies of tungsten-based materials through alloying, compounding, and dispersion strengthening are reviewed. The future research directions are put forward.