Inclined DROP test of A CC-440 packaging system

To safely transport radioactive materials it is required that the packaging system must be able to guarantee their containment and confinement (via its integrity assurance) avoiding any additional dose exposure (respect of ALARA principle). The engineering system has thus to be designed to ensure safety features by complying/satisfy specific safety requirements, like the IAEA Safety Standards No. TS-R-1 and No. SSR-6. In this framework, the present study is intended to investigate and analyse the performance of an Italian CC-440 package, for the transport of low and intermediate level radioactive waste, subjected to the inclined free drop test. To the purpose numerical analysis simulating the drop test and performed by the FEM MSC Marc code are presented and discussed. In doing that a validation analysis of the numerical tool, based on available experimental data, has been carried out. The results obtained, in terms of stress, strains, acceleration, etc., showed that even if the packaging system components suffered local deformation, the magnitude of these effects would not determine an unacceptable loss of the safety features.