VALIDATION OF NUMERICAL SIMULATION METHOD USING A 1/3-SCALE MODEL DROP TEST OF KN-18 SNF TRANSPORT CASK - Presentation

The KN-18 SNF (spent nuclear fuel) transport cask is a newly developed cask intended for the dry or wet transportation of up to 18 PWR spent nuclear fuel assemblies in South Korea. The structural performance of the KN-18 transport cask in normal and hypothetical accident conditions was demonstrated in the SAR(safety analysis report) by the analysis using state-of-theart finite element methods, and that will be presented in another paper given during this PATRAM. A series of actual drop tests using 1/3-scale model were carried out to verify the numerical simulation method used in the analyses and to confirm the impact characteristics of the cask. Total of five 9 m drop tests and two 1 m puncture tests were performed using one 1/3-scale cask model with four sets of impact limiters. Basically 1/3-scale model has same design with real cask except some inevitable differences in geometry between the scale model and the real cask for the reason of fabrication, operation, and etc. In order to provide a robust basis for verification, finite element analyses of the scale model cask in all the drop test conditions were carried out. The same numerical tool and analysis methodology used in the real cask analysis were used in the FE analyses of the scale model. To allow a robust comparison between test and analysis results, the analysis model represents the complete cask, and all of the components are explicitly modelled in three dimensions. This paper presents the dynamic impact characteristics of the cask from test and analysis results and the validation of numerical simulation method by showing the correlation between test and analysis results.