TY - JOUR
T1 - Experiments on axial-flow-induced vibration of a free-clamped/clamped-free rod for light-water nuclear reactor applications
AU - Cioncolini, Andrea
AU - Zhang, Shanying
AU - Nabawy, Mostafa R.A.
AU - Li, Hao
AU - Cooper, Dennis
AU - Iacovides, Hector
N1 - Publisher Copyright:
© 2023 Elsevier Ltd
PY - 2023/9/15
Y1 - 2023/9/15
N2 - The flow-induced vibration of a cantilever rod confined in a pipe and exposed to an axial water flow has been experimentally investigated using a simple test piece designed to be informative for water-cooled nuclear reactor fuel rods. The Reynolds number was varied between 7.43 k and 82.5 k: a range that significantly extends the scope of existing data. Measurements were carried out using non-contact techniques: fast video imaging was used to track the rod motion, whilst particle image velocimetry was employed to resolve the flow field. The sources of excitation that sustain the rod vibration include turbulent buffeting, movement-induced excitation, and flow separation at the rod tip, whilst the observed dynamic responses of the rod comprise a fuzzy period-1 motion, a flutter-like large-amplitude oscillation, and buckling. Since both the rod vibration and the flow field are measured, the present data are particularly suited for numerical methodology development and validation.
AB - The flow-induced vibration of a cantilever rod confined in a pipe and exposed to an axial water flow has been experimentally investigated using a simple test piece designed to be informative for water-cooled nuclear reactor fuel rods. The Reynolds number was varied between 7.43 k and 82.5 k: a range that significantly extends the scope of existing data. Measurements were carried out using non-contact techniques: fast video imaging was used to track the rod motion, whilst particle image velocimetry was employed to resolve the flow field. The sources of excitation that sustain the rod vibration include turbulent buffeting, movement-induced excitation, and flow separation at the rod tip, whilst the observed dynamic responses of the rod comprise a fuzzy period-1 motion, a flutter-like large-amplitude oscillation, and buckling. Since both the rod vibration and the flow field are measured, the present data are particularly suited for numerical methodology development and validation.
KW - Fluid-structure interaction
KW - Fretting wear
KW - Nuclear fuel rod
KW - Optical tracking
KW - Particle image velocimetry (PIV)
KW - Validation benchmark
UR - http://www.scopus.com/inward/record.url?scp=85154057706&partnerID=8YFLogxK
U2 - 10.1016/j.anucene.2023.109900
DO - 10.1016/j.anucene.2023.109900
M3 - Article
AN - SCOPUS:85154057706
SN - 0306-4549
VL - 190
JO - Annals of Nuclear Energy
JF - Annals of Nuclear Energy
M1 - 109900
ER -