According to GB 11806-2019, the work aims to perform numerical simulations of 9 m free-drop scenarios for a sealed radioactive source transport container and employ finite element analysis to evaluate the structural mechanical responses, stress distribution, deformation characteristics, and integrity of the inner basket under different impact orientations and then identify the most critical drop attitude to verify the structural integrity and containment safety of the container. A full-scale refined finite element model was developed through ABAQUS, incorporating bolt pre-tension, material strain-rate effects, and multiple constitutive models. An implicit-explicit sequential solution strategy was adopted to complete the impact dynamics calculations for five typical 9 m drop attitudes, followed by stress linearization, deformation, and equivalent plastic strain analyses. Under all five attitudes, the stresses in the containment boundary and its connecting bolts remained below the permissible values specified in the national standard. The equivalent plastic strains in the basket and its connecting bolts to the lead plug were far below the material fracture threshold, with no failure or fracture risk observed. However, the structural deformation and shielding container sway caused by corner impact were the most pronounced, which might affect the sealing performance of the containment boundary in subsequent thermal tests. The structural strength and containment capability of the radioactive source container meet the regulatory requirements under 9 m free-drop conditions. The corner drop with the center of gravity passing through the impact point is identified as the most severe simulation attitude, which can serve as a benchmark for impact mechanical assessment and design verification of this radioactive package.
Key words
radioactive source transport container /
free drop /
finite element simulation /
structural integrity /
containment safety
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