Development of core seismic analysis models for KNGR fuel assemblies associated with 0.3 g seismic loads Original Research Article

In order to evaluate the structural integrity of fuel assemblies associated with 0.3 g seismic loads in the Korean Next Generation Reactor (KNGR), detailed fuel assembly model and core series models with seven and 17 assemblies have been developed using the super-element capability of the msc/nastran code. The detailed fuel assembly model has been verified by comparison with the analysis results and test results. Non-linear transient analysis has been performed on the core series models. The detailed fuel assembly model and core series models for the KNGR developed with the msc/nastran code have a good correlation with test results and in-reactor impact behavior of fuel assemblies under applied seismic loads. Since the time histories considered in the transient analysis were generated from a seismic analysis of the System 80+ reactor internals that is reference plant of the KNGR based on 0.3 g ground motion, it is necessary to study further the evaluation for the KNGR fuel assembly and the models using the site specific time histories. It is expected that the further evaluation and some modifications can be performed effectively with the aid of the models developed in this study.