The conversion of research reactor fuel from highly enriched uranium (HEU) to low enriched uranium (LEU) is a global nonproliferation objective coordinated by the IAEA and the U.S. Department of Energy. The Forschungs-Neutronenquelle Heinz Maier-Leibnitz (FRM II) is among the reactors pursuing this transition, which requires a redesigned core geometry and a comprehensive reassessment of its neutronic, thermal-hydraulic, and thermomechanical behaviour. In this context, accurate prediction of the structural response of the fuel plates under nominal and accidental conditions is essential. This thesis investigates the integration of LS-DYNA into an existing one-way Fluid–Structure Interaction (FSI) workflow, extending its use to both implicit quasi-static and explicit transient structural analysis.