FEM Modeling of Reactor Core for Seismic Analysis Using Super-Element(Modeling & Simulation)

Abstract

In order to evaluate the structural integrity of fuel assemblies associated with seismic loads in a PWR reactor, detailed fuel assembly model and core series models with 7 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 of the analysis results and test results. Nonlinear transient analysis has been performed on the core series models. The detailed fuel assembly model and core series models for a PWR 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.