Session: FSI-02-02 Tube Arrays - 2

Paper Number: 106353

106353 - Flow-Visualization of a Prototypical Helical Coil Test Bundle Undergoing Vibrations 

Flow-Induced Vibrations (FIVs) have been of the upmost interest in the engineering community due to their large role in safety and reliability design in heat exchangers. This has especially been true in the nuclear sector as focuses have shifted to Small Modular Reactors (SMRs). These reactors aim to decrease the volumetric footprint of reactors, while maintaining a reasonable power output. To achieve this more compact heat exchangers and faster flow rates are implemented. These changes lead to larger vibrational amplitudes in the system and must be accounted for. This study utilizes Particle Image Velocimetry (PIV) to provide flow visualization of a prototypical section of a Helical Coil Steam Generator (HCSG) with a clockwise, counterclockwise tube rotation undergoing vibrations. The bundle of interest utilizes a canti-levered attachment approach in or to lower the natural frequency of the system. This lower natural frequency reduces the required flow velocity to achieve Fluid-Elastic Instabilities (FEIs), one of the primary causes of tube bundle failures undergoing FIVs. The interaction between the structural movement and flow field statistics are studied intensively in order to gain greater understanding of the FIV phenomenon. Several advanced analysis techniques are utilized in this pursuit such as: Proper Orthogonal Decomposition (POD), Wavelet, and spectral analysis.

Presenting Author: Noah Sutton Texas A&M University

Presenting Author Biography: Noah Sutton is a fourth year Ph.D. student attending Texas A&M University. He works at the Thermal Hydraulics Lab focusing on Flow-Induced Vibrations in the nuclear sector under the tutelage of Dr. Yassin Hassan.

Authors:

Noah Sutton Texas A&M University
Blake Maher Texas A&M University
Rodolfo Vaghetto Texas A&M
Yassin Hassan Texas A&M