Operational modal analysis of flow-induced vibration of nuclear fuel rods in a turbulent axial flow

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Operational modal analysis of flow-induced vibration of nuclear fuel rods in a turbulent axial flow. / De Pauw, Ben; Weijtjens, W.; Vanlanduit, Steve; Van Tichelen, Katrien; Berghmans, Francis.

In: Nuclear Engineering and Design, Vol. 284, 01.04.2015, p. 19-26.

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De Pauw, Ben ; Weijtjens, W. ; Vanlanduit, Steve ; Van Tichelen, Katrien ; Berghmans, Francis. / Operational modal analysis of flow-induced vibration of nuclear fuel rods in a turbulent axial flow. In: Nuclear Engineering and Design. 2015 ; Vol. 284. pp. 19-26.

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@article{2e41602cbbbe4abbad7a287971b8c5dd,
title = "Operational modal analysis of flow-induced vibration of nuclear fuel rods in a turbulent axial flow",
abstract = "Flow-induced vibration of nuclear reactor fuel pins can result in mechanical noise and lead to failure of the reactor's fuel assembly. This problem can be exacerbated in the new generation of liquid heavy metal fast reactors that use a much denser and more viscous coolant in the reactor core. An investigation of the flow-induced vibration in these particular conditions is therefore essential. In this paper, we describe an analysis technique to evaluate flow-induced vibration of nuclear reactor fuel pins subjected to a turbulent axial flow of heavy metal. We deal with a single fuel pin mockup designed for the lead–bismuth eutectic (LBE) cooled MYRRHA reactor which is subjected to similar flow conditions as in the reactor core. Our analysis is based on operational modal analysis (OMA) techniques. We show that the accuracy and precision of our OMA technique is higher compared to traditional methods and that it allows evaluating the evolution of modal parameters in operational conditions. We also demonstrate the possible onset of a fluid-elastic instability by tracking the modal parameters with increasing flow velocity.",
keywords = "flow-induced vibration, modal analysis, nuclear fuel",
author = "{De Pauw}, Ben and W. Weijtjens and Steve Vanlanduit and {Van Tichelen}, Katrien and Francis Berghmans",
note = "SCORE=10",
year = "2015",
month = "4",
day = "1",
doi = "10.1016/j.nucengdes.2014.11.040",
language = "English",
volume = "284",
pages = "19--26",
journal = "Nuclear Engineering and Design",
issn = "0029-5493",
publisher = "Elsevier",

}

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TY - JOUR

T1 - Operational modal analysis of flow-induced vibration of nuclear fuel rods in a turbulent axial flow

AU - De Pauw, Ben

AU - Weijtjens, W.

AU - Vanlanduit, Steve

AU - Van Tichelen, Katrien

AU - Berghmans, Francis

N1 - SCORE=10

PY - 2015/4/1

Y1 - 2015/4/1

N2 - Flow-induced vibration of nuclear reactor fuel pins can result in mechanical noise and lead to failure of the reactor's fuel assembly. This problem can be exacerbated in the new generation of liquid heavy metal fast reactors that use a much denser and more viscous coolant in the reactor core. An investigation of the flow-induced vibration in these particular conditions is therefore essential. In this paper, we describe an analysis technique to evaluate flow-induced vibration of nuclear reactor fuel pins subjected to a turbulent axial flow of heavy metal. We deal with a single fuel pin mockup designed for the lead–bismuth eutectic (LBE) cooled MYRRHA reactor which is subjected to similar flow conditions as in the reactor core. Our analysis is based on operational modal analysis (OMA) techniques. We show that the accuracy and precision of our OMA technique is higher compared to traditional methods and that it allows evaluating the evolution of modal parameters in operational conditions. We also demonstrate the possible onset of a fluid-elastic instability by tracking the modal parameters with increasing flow velocity.

AB - Flow-induced vibration of nuclear reactor fuel pins can result in mechanical noise and lead to failure of the reactor's fuel assembly. This problem can be exacerbated in the new generation of liquid heavy metal fast reactors that use a much denser and more viscous coolant in the reactor core. An investigation of the flow-induced vibration in these particular conditions is therefore essential. In this paper, we describe an analysis technique to evaluate flow-induced vibration of nuclear reactor fuel pins subjected to a turbulent axial flow of heavy metal. We deal with a single fuel pin mockup designed for the lead–bismuth eutectic (LBE) cooled MYRRHA reactor which is subjected to similar flow conditions as in the reactor core. Our analysis is based on operational modal analysis (OMA) techniques. We show that the accuracy and precision of our OMA technique is higher compared to traditional methods and that it allows evaluating the evolution of modal parameters in operational conditions. We also demonstrate the possible onset of a fluid-elastic instability by tracking the modal parameters with increasing flow velocity.

KW - flow-induced vibration

KW - modal analysis

KW - nuclear fuel

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/12409282

U2 - 10.1016/j.nucengdes.2014.11.040

DO - 10.1016/j.nucengdes.2014.11.040

M3 - Article

VL - 284

SP - 19

EP - 26

JO - Nuclear Engineering and Design

JF - Nuclear Engineering and Design

SN - 0029-5493

ER -

ID: 1003503