Abstract
Flow induced vibration (FIV) is a phenomenon resulting from the interaction of fluid flows and relatively flexible structures. In nuclear power plants, in particular, the high velocity coolant fluids through very slender components such as fuel rods or exchanger tubes can induce detrimental component vibration and instability. In this work, a numerical study of FIV of nuclear fuel rods in axial turbulent flows is performed using a combined computational fluid dynamics (CFD) and computational structural mechanic (CSM) approach. Simulations of the FIV of a single bare rod in water fluid flow are performed and its modal parameters are analized. Then the effects of the wire spacer on FIV are then studied in the case of water and liquid metal fluid flows.
| Original language | English |
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| State | Published - 2017 |
| Externally published | Yes |
| Event | 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017 - Xi'an, Shaanxi, China Duration: 3 Sep 2017 → 8 Sep 2017 |
Conference
| Conference | 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017 |
|---|---|
| Country/Territory | China |
| City | Xi'an, Shaanxi |
| Period | 3/09/17 → 8/09/17 |
Bibliographical note
Publisher Copyright:© 2016 Association for Computing Machinery Inc. All Rights Reserved.
Keywords
- Flow-induced vibration
- Fluid-structure interaction
- Turbulent flow
- Wire-wrapped rods
ASJC Scopus subject areas
- Nuclear Energy and Engineering
- Instrumentation