Research Papers: Fluid-Structure Interaction

Evaluation of the Integrity of Steam Generator Tubes Subjected to Flow Induced Vibrations

[+] Author and Article Information
Marwan Hassan

School of Engineering,
University of Guelph,
Guelph, ON N1G 2W1, Canada
e-mail: mahassan@uoguelph.ca

Jovica Riznic

Operational Engineering Assessment Division,
Canadian Nuclear Safety Commission,
Ottawa, ON K1P 5S9, Canada
e-mail: jovica.riznic@cnsc-ccsn.gc.ca

1Corresponding author.

Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received August 29, 2013; final manuscript received February 13, 2014; published online August 19, 2014. Assoc. Editor: Samir Ziada.

J. Pressure Vessel Technol 136(5), 051301 (Aug 19, 2014) (11 pages) Paper No: PVT-13-1150; doi: 10.1115/1.4026982 History: Received August 29, 2013; Revised February 13, 2014

Flow-induced vibrations (FIV) continue to affect the operations of nuclear power plant components such as heat exchanger tube bundles. The negative effect of FIV is in the form of tube fatigue, cracking, and fretting wear at the supports. Fretting wear at the supports is the result of tube/support impact and friction. Fluidelastic and turbulence forces are the two main excitation mechanisms that feed energy into the system causing these violent vibrations. To minimize this effect all support clearances must be kept at a very small value. This paper investigates the consequences of losing the effectiveness of a particular support as a result of corrosion or excessive fretting wear. A full U-bend tube subjected to both fluidelastic and turbulence forces is utilized in this work. The performance of countermeasures such as the installation of additional flat bars in the U-bend region is thoroughly investigated. The investigation utilized both deterministic and probabilistic techniques.

Copyright © 2014 by ASME
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Fig. 1

Nuclear steam generator: (a) a typical overall view and (b) finite element model and flow distribution

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Fig. 2

Flow cell model in the U-bend region

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Fig. 3

Loose support configurations and models

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Fig. 4

Nonlinear model configurations: (a) configuration 1, (b) configuration 2, and (c) configuration 3

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Fig. 5

Linear mode shapes

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Fig. 6

Linear simulations: (a) predicted tube rms response versus flow velocity, (b) the predicted critical flow velocity versus available experimental data: * Soper [24]; • Hartlen [25]; ♦ Weaver and Grover [26]; ◇ Connors [27]; △ Pettigrew et al. [28]; □ Heilker and Vincent [29]; ⊳ Gorman [30]; ☆ simulations

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Fig. 7

Work rate results for configuration 1 varying H07 clearance: (a) U-bend clearance = 0.1 mm and (b) U-bend clearance = 0.2 mm

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Fig. 8

Work rate results for configuration 3 with varying clearance at: (a) scallop bars S1A and S1B, (b) flat bars F1 and F2, and (c) scallop bars S2A and S2B

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Fig. 9

Tube support radial clearances and offsets: (a) broached-hole support, (b) scallop bar support, and (c) flat-bar support

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Fig. 10

Impact force histograms for U-bend supports

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Fig. 11

Relationship between individual support clearance and the impact force

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Fig. 12

Relationship between support S2A clearance and the impact force

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Fig. 13

Work rate histograms for U-bend supports

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Fig. 14

Relationship between individual support clearance and the work rate

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Fig. 15

Relationship between support S2A clearance and the work rate




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