In this pilot scale testing research, two typical intermediate and low level radioactive wastes from the nuclear power plant were vitrified with thermal plasma. Both samples were melted at 1250℃ for 100min, and the XRD patterns of both samples presented as the typical amorphous state. Co2O3, SrCO3,CsCl were been added to the original wastes as the radionuclide tracer for simulating the containment effect of radionuclide in the process of vitrification. The performance of physical, leaching and mechanical of resultant glass waste-forms were tested showing the comparable requirement with the hign level radioactive waste glasses and the better one than cement waste-form. Finally, we discussed the prospect of the current work and proposed issues to be resolved.