SUMMARY

Development of a coupled quasi-steady state multiphysics solver package linking neutron transport, computational fluid dynamics, and flow-induced vibration effects (such as fluid-elastic instability criteria and fuel rod fretting) for a uranium silicide fuel pin for the I2S-LWR reactor concept is the focus of this dissertation. Investigation of Flow-Induced Vibration (FIV) driven thermal hydraulics and radiation transport driven neutronics will be performed using the Computational Fluid Dynamics (CFD) code ANSYS Fluent, the 3D discrete-ordinates neutron transport code PENTRAN, the cross section generation code DRAGON, and the Flow-Induced Vibrations code FIVEPINS. Fuel performance parameters will be shared between all of these codes in a coupled system. Previous research has generated a detailed Single Channel Analysis model and a 2D CFD full height pin model.