Low-medium level radioactive solid waste cask drop analysis and test

Objective: To understand the effectiveness of finite element analysis in verification of the mechanical property of nuclear power plant equipment. The cask was designed to ship low-medium level radioactive solid waste of nuclear power plant. The China standard EJ1076-1998 demanded to maintain the cask integrity after the drop test. Methods: A simulation of drop process used nonlinear Finite element code MARC was carried out . And a drop test of the cask was done afterwards. Results: The drop test showed: the corner of the container was destroyed and the seal of the container was destroyed. The finite element analysis got the same results as the drop test. The results of analysis were instrumental in the success of the drop tests. And these results also had been validated by the drop test. Conclusion: The nonlinear finite element analysis can effectively predict the mechanical property of the cask drop process. This paper described the process of FEA, and compared the analysis results with the test results. (author)