目的 依据GB 11806—2019,针对某密封放射源运输容器,开展9 m自由下落工况的数值模拟研究,依靠有限元仿真评估不同着地姿态下结构的力学响应、应力分布、变形特征及内吊篮完整性,选取最危险下落姿态,确认容器的结构完整性与包容安全性。方法 基于ABAQUS构建全尺寸精细化有限元模型,涵盖螺栓预紧、材料应变率效应及多元本构特性,通过隐式-显式转换求解策略完成5种典型9 m下落姿态的冲击动力学计算,并对应力线性化、变形量、等效塑性应变进行分析。结果 5种姿态下包容边界及其连接螺栓的应力均低于评价准则的许用限值,吊篮及其与铅塞连接螺栓的等效塑性应变远在材料断裂阈值之下,未发生破坏或断裂风险,而底角冲击引起的结构变形与屏蔽容器偏摆最为显著,这将会导致后续耐热试验对包容边界密封性能造成影响。结论 该放射源容器在9 m自由下落条件下结构强度与包容能力均符合规范要求,底角过重心下落为最严苛仿真姿态,可作为该放射性货包冲击力学评估与设计校核的基准。
Abstract
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.
关键词
放射源运输容器 /
自由下落 /
有限元仿真 /
结构完整性 /
包容安全性
Key words
radioactive source transport container /
free drop /
finite element simulation /
structural integrity /
containment safety
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