An experimental investigation of effects of angular misalignment on flow-induced vibration of simulated CANDU fuel bundles

Bhattacharya, Arya K.; Yu, S. D.

doi:10.1016/j.nucengdes.2012.06.024

Cited by 8 publications

(4 citation statements)

References 12 publications

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“…To demonstrate this, various flow parameters, like flow velocities, fluid excitaion force, for each fuel bundle, are considered for analysis and discussion. It is observed from earlier studies (Zhang and Yu, 2011;Bhattacharya et al, 2012a), that the fluid excitaions for bundle lateral motion primarily come from the region around the endplates, i.e., the inlet and the interface zones, where the flow is mainly mixed of cross and parallel flow, compared to the almost parallel flow at the mid-bundle locations. Thus, the analysis in the subsequent sections will be done for parameters in transverse, i.e., x and y direction, with z being the longitudinal or axial direction of the flow model.…”

Section: Resultsmentioning

confidence: 95%

“…They also noticed the formation of large eddies and swirling flow behind the inlet endplate. In some other intersting works, it has been observed that endplates are one of the major sources for the bundle transverse vibration (Zhang and Yu, 2011;Bhattacharya et al, 2012a). Very recently, Bhattacharya et al, (2011b), Bhattacharya and Yu (2012a), Bhattacharya and Yu (2012b) found that the angular misalignment between neighbouring bundles can significantly increase the bundle transverse motion induced by the flow and also the lateral fluid excitations on the fuel bundles.…”

Section: Approach With Computational Fluid Dynamicsmentioning

confidence: 98%

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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: Resultsmentioning

confidence: 95%

Section: Approach With Computational Fluid Dynamicsmentioning

confidence: 98%

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

Bhattacharya¹

2023

Preprint

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“…Therefore, a thorough analysis of flow-induced vibration of the fuel pins is a crucial aspect of the design cycle in view of assessing the lifetime of reactor internals and ensuring safe operation of these reactors. Different vibration sensors or techniques are available to carry out such measurements [12][13][14][15]. However, we had to work in liquid LBE, which has a density of more than 10 times that of water, is corrosive and opaque [16].…”

Section: Introductionmentioning

confidence: 99%

Characterizing Flow-Induced Vibrations of Fuel Assemblies for Future Liquid Metal Cooled Nuclear Reactors Using Quasi-Distributed Fibre-Optic Sensors

et al. 2017

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Excessive vibration of nuclear reactor components, such as the heat exchanger or the fuel assembly should be avoided as these can compromise the lifetime of these components and potentially lead to safety hazards. This issue is particularly relevant to new reactor designs that use liquid metal coolants. However, identifying adequate sensors or techniques that can be successfully applied to record the vibrations of the components in a flow of liquid metal at elevated temperatures is very challenging. In this paper, we demonstrate the precise measurements of the vibrations of a very representative mock-up of a fuel assembly in a lead-bismuth eutectic cooled installation using quasi-distributed fibre Bragg grating (FBG) based sensors. The unique properties of these sensors, in combination with a dedicated integration and mounting approach, allows for accounting of the severe geometrical constraints and allows characterizing the vibration of the fuel assembly elements under nominal operation conditions. To that aim, we instrumented a single fuel pin within the fuel assembly with 84 FBGs, and conducted spectral measurements with an acquisition rate of up to 5000 measurements per second, enabling the monitoring of local strains of a few µε. These measurements provide the information required to assess vibration-related safety hazards.

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“…Pettigrew 2 studied the vibration of the fuel assembly under internal axial flow and found that it tends to vibrate near its natural frequency and that vibration amplitude increases proportional to the flow velocity to the second or third power. Hassan and Hayder, 3 Sigrist and Broc, 4 Kuehlert et al, 5 Longatte et al, 6 and others have performed extensive research on the flow-induced vibration of steam generators by means of both simulation and experimentation; Bakosi et al, 7 Mohany and Hassan, 8 and Bhattacharya and Yu 9 mainly examined the fuel rod under flow-induced vibration. Recently, Rahman et al 10 analyzed hydraulic force (lift-off and hold-down force) of three types of high-performance annular fuels and found that the hydraulic force acting on the fuels was affected greatly by the configuration of fuels.…”

Section: Introductionmentioning

confidence: 99%

Investigation of hydraulic force of a 1000-MW pressurized water reactor under hypothetical drop accident of core barrel assembly

Jiang

Zhang

et al. 2016

Advances in Mechanical Engineering

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In this study, we conducted a simulation investigation of a hypothetical core barrel assembly drop accident based on the dynamic mesh model. The investigation included three separate circumstances: high-temperature dynamic water, hightemperature still water, and low-temperature still water. Results showed that dynamic parameters (e.g. velocity and resultant force) of the drop assembly in high-temperature dynamic water are smaller than those in still water due to the buffer effect of the flowing water. The velocity and hydraulic force in the dynamic water situation increased quickly at first and then remained stable throughout the remainder of the experiment; due to turbulence effect, the hydraulic force fluctuated slightly, first increased, then decreased, and then reached as stable a level in still water as that in dynamic water. The velocity of the drop assembly showed parabolic growth.

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An experimental investigation of effects of angular misalignment on flow-induced vibration of simulated CANDU fuel bundles

Cited by 8 publications

References 12 publications

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

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

Characterizing Flow-Induced Vibrations of Fuel Assemblies for Future Liquid Metal Cooled Nuclear Reactors Using Quasi-Distributed Fibre-Optic Sensors

Investigation of hydraulic force of a 1000-MW pressurized water reactor under hypothetical drop accident of core barrel assembly

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