Abstract: FCTC10 container is designed to transport cobalt-60 radioactive sources used in irradiation industry. It belongs to type B (U) grade Ⅲ (yellow) package when being loaded with a cobalt-60 source of 180 thousands curie. The container is constituted by shielding container, basket, protective cover, and bracket. Shielding ability is provided mainly by stainless steel shells, tungsten alloy and lead among steel shells. Radiation level around the container with maximum load are given through both Monte Carlo method simulation calculation and experiment measurement. It is proven that the shielding performance of the container is complied with the requirements in GB 11806—2004. Exposure doses of workers and public key groups are given based on hypothetical exposure scene according to transport practice experience. The results show that exposure doses of the workers and the public are less than the constraint dose considered in design, and also lower than dose limit regulated in GB 18871—2002. The dose received by the responders will be small becouse the increase of radiation level outside the container is tess than one time under design basis accidents.

Key words: irradiation industry, radioactive source, transport container, shielding, measurement and assessment