This study investigates the computational modelling of flow-induced vibrations of cantilever
rods subjected to turbulent axial flow at operating conditions relevant to those of fuel rods of …

Flow-induced vibration (FIV) characteristics of LBE-cooled wire-wrapped rod bundle are
crucial to the wire-to-cladding fretting. In the present study, numerical simulation on FIV of …

This study presents a simulation method for turbulent flow-induced vibrations of cantilever
rods with a semi-spherical end exposed to axial flow, a configuration investigated for the first …

Abstract In this work, Fluid-Structure Interaction (FSI) simulations are performed to study
Flow Induced Vibrations (FIV) of nuclear fuel rods using the commercial code STAR-CCM+ …

Abstract MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) is a
prototype of a Generation IV reactor that will be constructed in Mol, Belgium. It is a liquid …

In this work, an advanced solver for the simulation of Fluid-Structure Interaction (FSI)
problems for nuclear applications is presented. The numerical framework, called as NRG …

This paper aims to investigate and present the numerical investigation of airflow
characteristics using Turbulent Kinetic Energy (TKE) to characterize the upper airway with …

Wire-wrapped fuel rods are widely utilized in lead-bismuth reactors and subjected to high
kinetic energy fluid flow, significantly influencing the reactor's safe operation. This study …

A significant aspect of the economic performance and safety of a nuclear reactor involves
maintaining the integrity of the fuel rods, which are susceptible to Turbulence-Induced …

Abstract Knowledge of the heat transport in the core is important for design and safety
assessment of all nuclear reactors including liquid metal cooled reactors. In the past, design …