The work aims to provide reference and suggestions for shielding performance evaluation of radioactive material transport container. With a typical large-capacity radioactive source transport container as the research object, 3 shielding evaluation methods (formula calculation, Monte Carlo software calculation and shielding test) commonly used in radioactive protection were employed to evaluate the shielding performance of the container and the radiation dose rate generated by the 60Co radioactive source (12 000 Ci) of the same activity at the designated location outside the container was given. The 60Co radioactive source (12 000 Ci) and the radiation measuring instrument were used to directly test the shielding performance of the research object, and the external radiation level when the specified 60Co radioactive source was loaded was obtained through conversion, and the measured results were compared with the calculated results. 3 different methods were used to obtain the radiation level at a specified location outside the same transport container loaded with the same contents. Formula calculation was the most convenient and fast. The results calculated by Monte Carlo software were closer to the measured results. The results obtained by direct measurement with radioactive sources were the most intuitive and reliable, but were greatly affected by the measuring environment and instruments. The results obtained by 3 calculation methods and the measured results are slightly different in numerical value, but they are all in the same order of magnitude and can be used to evaluate the shielding performance of the radioactive material transport container.