Numerical study of flow-induced vibration of nuclear fuel rods

D. de Santis, A. Shams*

*Corresponding author for this work

Research output: Contribution to conferencePaperpeer-review

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+. The Navier-Stokes equations are solved on deforming grids with the Arbitrary Eulerian-Lagrangian (ALE) formulation. The finite element method is used to solve the linear elastic problem for the structure. The two solvers are tightly coupled together with the Gauss-Seidel method to solve the FSI problem. The first part of the work focuses on the FIV of a single rod. Two types of rods are considered: 1) a bare rod and 2) a rod with a wire spacer helically wrapped around its external surface. For the case of the bare rod configuration, the effects of the working fluid on the dynamics is investigated and a correlation for the frequencies as function of density is proposed. The second part of the work focuses on the analysis of FIV for two different configurations of bare seven-rod bundle. One of the main features of the considered configurations is the appearance of axial flow fluctuations in the rod gaps due to the velocity difference in the sub-channels between the rods. Therefore, this part of the work focuses on the study of the effect of the velocity pulsations on the vibrations of the rods.

Original languageEnglish
Pages5078-5091
Number of pages14
StatePublished - 2019
Externally publishedYes
Event18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 - Portland, United States
Duration: 18 Aug 201923 Aug 2019

Conference

Conference18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019
Country/TerritoryUnited States
CityPortland
Period18/08/1923/08/19

Bibliographical note

Publisher Copyright:
© 2019 American Nuclear Society. All rights reserved.

Keywords

  • Flow induced vibration
  • Fluid-structure interaction
  • Rod bundles
  • Wire spacer

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Instrumentation

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