Equivalent drop analysis model of transportation cask including spent nuclear fuel assembly

The purpose of this study is to develop an equivalent analysis model for evaluating the integrity of a spent fuel cladding tube from drop impacts under normal transport conditions and accident conditions of a transportation cask. This study proposes the equivalent drop analysis FE model of the transportation cask including the spent nuclear fuel assembly under normal transport and accident conditions, and a verification test was performed for showing the reliability of the equivalent analysis model. This study presents the equivalent finite element model for the vertical drop analysis of the transportation cask including the spent nuclear fuel assembly under normal transport and accident conditions. The analysis results showed that the present equivalent FE model had the reliability by comparing with the drop analysis results using the detailed FE model