Prediction of pressure tube fretting-wear damage due to fuel vibration

Yetisir, M.; Fisher, N. J.

doi:10.1016/s0029-5493(97)00149-0

Cited by 27 publications

(9 citation statements)

References 8 publications

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“…Therefore, it was believed that turbulence-induced excitations may produce enough bundle vibration to cause wear in the supporting tube. However, Yetisir and Fisher (1997) pointed out that the small scale parallel-flow turbulence alone is not sufficient to produce the required level of bundle vibration and work-rate for the observed fretting marks on the pressure tube surface. Moreover, some recent studies report that the mixed parallel and cross flow through the various bundle subchannels and bundle interfaces can act as a potential source of FIV of fuel bundles (Zhang and Yu, 2011;Bhattacharya et al, 2011a;Bhattacharya et al, 2012).…”

Section: Fuel Bundle Vibration Phenomenonmentioning

confidence: 99%

“…Pettigrew (1993), in an experimental investigation on CANDU fuel bundle vibration, reported that the vibration amplitudes increase with the mass flow rates and the recorded RMS values of vibration response was within 10 μm. Yetisir and Fisher (1997) developed an analytical model for a single fuel element subjected to turbulence excitation modeled by random excitation forces applied uniformly on the fuel element. They found that the fuel element vibration due to the flow-induced random turbulent excitation is insufficient by itself to produce the required level of work rate causing the fretting damage observed in some commercial CANDU reactors.…”

Section: Analytical and Experimental Studymentioning

confidence: 99%

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Investigations on Flow and Flow-Induced Vibration of CANDU Fuel Bundles

Bhattacharya¹

2023

Preprint

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Excitations induced by three-dimensional unsteady flows of ordinary water coolant through a string of CANDU fuel bundles in a fuel channel are investigated in this thesis. Several comprehensive computational fluid dynamics (CFD) models are developed and solved by means of large eddy simulation (LES), high performance computers and parallel processing scheme. The 12-bundle flow model is the first ever developed concerning flow in a very complex CANDU fuel channel. The lateral fluid flow and flow-induced excitations on every fuel bundle are obtained and analyzed for various combinations of bundle angular positions. The coherent nature of the flow through the multiple bundles inside the fuel channel exhibiting fluid excitations of frequencies spreaded over a wide band in the power spectra is a source of bundle lateral vibration. The flow features of different bundle regime are correlated both in time and frequency domain and they are sensitive to the bundle-to-bundle angular position. This finding directs that, to study the flow and flow-induced excitations and vibrations of a bundle string, it is necessary to include all bundles for fluid-structure interactions. Results from the computational model reveal that the misaligned interface changes the flow pattern in the fuel channel. The mean lateral fluid forces increase by an order of magnitude and their RMS values raise about 3 to 4 times at some configurations compared to fully aligned situation. Experiments are also performed using the simulated CANDU bundles in an out-reactor setup to verify the computational results. An analysis of a complete fuel channel of a nuclear reactor using LES is at the forefront of current research worldwide and this study is a major step forward towards understanding and unfolding the fuel bundle vibration phenomenon.

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Section: Fuel Bundle Vibration Phenomenonmentioning

confidence: 99%

Section: Analytical and Experimental Studymentioning

confidence: 99%

Investigations on Flow and Flow-Induced Vibration of CANDU Fuel Bundles

Bhattacharya¹

2023

Preprint

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“…This is confirmed by the author through experiments (Zhang and Yu, 2008). Turbulence in parallel flows inside the bundle was regarded as the cause of vibration in the past; however it was proven that turbulence in the fully developed flow in a fuel bundle was insufficient to excite an individual fuel element to vibrate at the level that leads to the pressure tube fretting marks observed in the Darlington and Bruce reactors (Yetisir and Fisher, 1997). This indicates that an unknown stronger source of excitation must exist in the bundle flow.…”

Section: Pressure Tube Fretting and Fuel Bundle Vibrationmentioning

confidence: 99%

“…Random vibration response of a fuel element in a turbulent parallel two-phase flow was modeled by Gorman (1971) with the measured statistical properties of the twodimensional pressure field surrounding the fuel element. Yetisir and Fisher (1997) presented a similar model for an individual CANDU fuel element in a turbulent flow that represents the typical fully developed flow inside a fuel bundle. They found that turbulence cannot excite the fuel element vibration to the level that can produce the observed fretting marks.…”

Section: Flow-induced Vibration Of Fuel Bundlesmentioning

confidence: 99%

Numerical and experimental investigations on vibration of simulated CANDU fuel bundles subjected to turbulent fluid flow

Zhang¹

2021

Preprint

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Vibration of simulated CANDU fuel bundles induced by coolant flow is investigated in this thesis through experiments and numerical simulations. Two simulated bundles and a hydraulic loop are built to mimic the situation of the fuel bundles located at the inlet of a fuel channel in a CANDU nuclear reactor. Fuel bundle vibration mechanism is investigated through experiments and numerical simulations. The three-dimensional turbulent flow that passes through the simulated bundles is modeled using the large eddy simulation (LES) and solved with parallel processing. The local cross flows induced by the presence of endplates at the inlet location and bundle interface location are investigated. The fluid forces are obtained as excitations for the fuel bundle vibration analysis. A finite element model of the fuel bundles is developed with the endplates modeled using the 3rd order thick plate theory. The response of the inlet fuel bundle to the fluid excitations is solved in the time and the frequency domain. The added mass and the fluid damping are approximated with the theory on the flow-induced vibration of slender bodies in a parallel flow. Measurements are obtained and used to validate the numerical prediction under various operating flow conditions.

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“…W n is normalized by the input power induced by turbulence, W tur and the total power absorbed by a tube of length, L. Mass per unit length, m, was expressed by Yetisir and Fisher (1997).…”

Section: Dimensionless Parametersmentioning

confidence: 99%

An investigation of impact-sliding behavior and fretting wear of tubes against different supports in steam generators

Guo

Han

Wang

et al. 2020

ILT

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Purpose The purpose of this study is to reveal the interaction behavior between tubes and supports in steam generators and study the fretting wear of tubes in different load conditions. Design/methodology/approach The fretting wear tests were conducted to investigate the fretting wear behavior of the tubes against three kinds of supports: the drilled circular holes (DCH), anti-vibration bars (AVBs) and trefoil orifice holes (TOH), which are widely used supports in nuclear steam generators. In this paper, the comparison of the interaction characteristic with different impact factors was established such as clearances and loads in the three kinds of supports. The fretting wear volume and scars were analyzed by a scanning electron microscope and 3D profiler. Findings The results show that impact can play a more important role in the DCH and TOH supports than that in AVBs. The normal work rate can be underestimated in the DCH and TOH supports. Originality/value The results of this study can be reference of fretting wear calculation in the design of steam generators with different kinds of supports and can be guidance in the maintenance of steam generators. Peer review The peer review history for this article is available at: https://publons.com/publon/10.1108/ILT-12-2019-0513/

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Prediction of pressure tube fretting-wear damage due to fuel vibration

Cited by 27 publications

References 8 publications

Investigations on Flow and Flow-Induced Vibration of CANDU Fuel Bundles

Investigations on Flow and Flow-Induced Vibration of CANDU Fuel Bundles

Numerical and experimental investigations on vibration of simulated CANDU fuel bundles subjected to turbulent fluid flow

An investigation of impact-sliding behavior and fretting wear of tubes against different supports in steam generators

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