Numerical modeling of flow induced vibration of nuclear fuel rods

Santis, Dante De; Shams, A.

doi:10.1016/j.nucengdes.2017.05.013

Cited by 50 publications

(5 citation statements)

References 27 publications

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“…To establish a better understanding of the dynamics of the flow-induced vibration for nuclear applications, most earlier studies focused on flexible rods which result in larger displacements [3]. Meanwhile, to reduce complexity, the nuclear fuel rod is commonly simplified as a single material [3], while others modelled the rod with solid lead-bismuth at the centre to represent the fuel pellets [4]. The MACE FIV experiments, on the other hand, shown in figure 1 (a) and (b) used variable-sized lead spheres filled in a steel cladding with similar packing factor as the uranium fuel pellet used in the nuclear fuel rod [2], and the results on the 1st mode of vibration proved good agreement with the analytical Euler-Bernoulli beam theory, by assuming that the flexural rigidity is calculated based on the geometry of the cladding only, neglecting the effects of the lead-spheres.…”

Section: Literature Reviewmentioning

confidence: 99%

“…Equations ( 1) to (4) showed that the density of the rod is inversely proportional to the frequency of vibration and proportional to the elasticity and cross-section area of the rod. With constant 1st mode of vibration, two solid models were proposed, the solid cylinder low elasticity (SLE) and the empty cladding high density (EHD).…”

Section: Euler-bernoulli Beam Theorymentioning

confidence: 99%

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Pragmatic modelling of axial flow-induced vibration (FIV) for nuclear fuel rods

Pauzi

Iacovides

Cioncolini

2023

IOP Conf. Ser.: Mater. Sci. Eng.

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Flow-induced vibration (FIV) at the spacer grid in the fuel assembly of a Light Water Reactor (LWR) is the leading cause of fuel failure. This project aims to produce a simulation benchmark on the experimental campaign at MACE on axial FIV of a cantilever beam in an annular tube, that mimics the configuration and environment of a typical LWR. The nuclear fuel rod, which consists of fuel pellets filled in Zirconium alloy cladding is modelled in the experiment as a steel rod filled with lead shots that closely approximates the filling density of the fuel pellet. To reduce the complexity and increase the efficiency of the simulation, further simplification is applied by on the geometry and assuming the solid domain as a single material instead of multiple materials. The first mode of frequency of the rod vibrating in quiescent water, which had been validated via the Euler-Bernoulli beam theory against experimental measurements, was used to design the single-material solid domain. Two models were proposed, firstly a solid rod with lower density and stiffness (SLE), and secondly an empty cladding with high density and low stiffness (EHD). Both solid and fluid domains were discretised using the cell-centred finite volume (FV) method and coupled with strong two-way fluid-structure interaction (FSI). Results on the frequency of vibration in quiescent water and in axial flow showed good agreement with experimental measurement, and the computational efficiency is analyzed for different rod models and changes in parameters of the solid domains.

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Section: Literature Reviewmentioning

confidence: 99%

Section: Euler-bernoulli Beam Theorymentioning

confidence: 99%

Pragmatic modelling of axial flow-induced vibration (FIV) for nuclear fuel rods

Pauzi

Iacovides

Cioncolini

2023

IOP Conf. Ser.: Mater. Sci. Eng.

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“…The results compared well against experiments and linear theory and have the advantage of being independent of empirical coefficients that appear in the fluid forces used in linear theory. Other examples can be found in the work of De Santis et al [32,33], in which the natural frequencies and damping ratios of cylinders in axial flow were determined. For a cluster of cylinders, the dynamics become more complex due to the inter-cylinder coupling caused by the presence of the fluid [34,35].…”

Section: Introductionmentioning

confidence: 99%

A multi-stage approach of simulating turbulence-induced vibrations in a wire-wrapped tube bundle for fretting wear prediction

Dolfen

Ridder

Brockmeyer

et al. 2022

Journal of Fluids and Structures

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“…Structures subjected to an axial or transverse flow are common in many processes related to energy generation and conversion. One important phenomenon limiting the development and reliability of these applications is related to flow-induced vibration (FIV), which arises from the fluid-structure coupling (Kaneko et al, 2014;de Santis and Shams, 2017). FIV is one of the factors that would also endanger the operation safety of nuclear power plants (Liu et al, 2017;Ferrari et al, 2020).…”

Section: Introductionmentioning

confidence: 99%

Investigation on vibration response characteristics and influencing factors of the fuel rods of EPR

et al. 2022

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First, the theory of wet modal analysis and vibration response analysis are introduced, and the semi-empirical vibration equation is derived in this article. Then, the structural models of the fuel rod of M310 and EPR are introduced, and the fuel rod is simplified to a multi-span continuous simply supported beam model subject to multi-point constraints. The fuel rod is simplified as a simply supported beam, and the springs and dimples are equivalent to elastic constraints. In addition, based on ANSYS-APDL, the wet modal analysis and response analysis of fuel rods are carried out. The modal information and transverse vibration response of the fuel rod of M310 and EPR are compared. In addition, combined with the actual operating conditions of EPR, the effects of different transverse and axial flow velocities on the transverse vibration response are discussed. Finally, different failure conditions are designed to explore the impact of clamping failure on the vibration characteristics of the fuel rod of EPR. The results have shown that compared with the fuel rod of M310, the fuel rod of EPR has a lower natural frequency and larger amplitude; the transverse flow velocity has a greater impact on the transverse vibration response; grid failure would reduce the natural frequency of fuel rods, and different positions of failure have different effects on the different-order natural frequencies of fuel rods.

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Numerical modeling of flow induced vibration of nuclear fuel rods

Cited by 50 publications

References 27 publications

Pragmatic modelling of axial flow-induced vibration (FIV) for nuclear fuel rods

Pragmatic modelling of axial flow-induced vibration (FIV) for nuclear fuel rods

A multi-stage approach of simulating turbulence-induced vibrations in a wire-wrapped tube bundle for fretting wear prediction

Investigation on vibration response characteristics and influencing factors of the fuel rods of EPR

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