A Kind of Shielding Design and Verification Test of Radioactive Source Transport Container

Abstract A transport container for radioactive sources has been meticulously designed to facilitate the global transfer of radioactive materials from storage facilities to end-users. In compliance with the stipulations outlined in GB 11806 and the IAEA SSR-6, the radiation dose of the container was meticulously calculated under both normal transport conditions and accident scenarios. Shielding tests were conducted both at the manufacturing site and post-manufacturing. The results of these tests indicated that the surface dose rate was 289 μSv/h prior to testing, which increased to 299.34 μSv/h after testing. Additionally, the radiation level at a distance of 1 meter from the package was measured at 31.59 μ Sv/h. Both the computational and experimental outcomes confirm that the shielding design of the transport container adheres to the relevant standards set forth by GB 11806 and SSR-6.