Fluidelastic instability analysis of operating nuclear steam generator U-tubes

Jo, Jong Chull; Shin, Won

doi:10.1016/s0029-5493(99)00173-9

Cited by 16 publications

(2 citation statements)

References 10 publications

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“…Failure of the heat transfer tube is outstanding issues for the steam generator design and manufacture. For effectively monitoring the steam generator health, solve many basis problems associated with failure of the heat transfer tube is very important, such as the vibration mechanism and related structural dynamics [1][2][3][4][5][6]. The tube diameter is nearly 5m in Large-capacity steam generator U-tube section, U-shaped bend radius is very large range from 0 to 2.5m which of affect is clear to heat transfer tube vibration.…”

Section: Intorductionmentioning

confidence: 99%

Analysis on the Effect of Bend Curve Radius to Inherent Characteristics of the U-Tubes

Zhang

Liu

2012

AMR

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For large-capacity steam generator, piping zone diameter of U-tube section is nearly 5m, the range of U-shaped bend radius is very large from Zero meters to 2.5 meters, this affects obviously the Vibration characteristics of heat transfer tube, this effect is researched using numerical simulation. Engineering formulas of natural frequency of U-shaped tube under different conditions are given. According the vibration-type, The lowest natural frequency of U-shaped tube is plane vibration frequency of the first order for adding one anti-vibration bar or not. Natural frequency of U-shaped tube increases significantly adding anti-vibration bars to bend, which is favorable to avoid the resonance frequency and severe vibration of U-shaped tube

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Section: Intorductionmentioning

confidence: 99%

Analysis on the Effect of Bend Curve Radius to Inherent Characteristics of the U-Tubes

Zhang

Liu

2012

AMR

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“…Ferng and Ma 7 and Ferng and Chang 8 considered the secondary vapor–liquid two-phase flow domain as a porous media domain—but without the addition of TSPs—and simplified the primary heating as an internal heat source in the SG to ultimately analyze secondary side thermal–hydraulic behaviors and predict the distribution of FIV damage in the U-bend region. Jo and Shin 9 and Jo et al. 10 performed a thermal–hydraulic analysis to provide a detailed three-dimensional two-phase flow field in the SG secondary region, but again without regard to TSPs.…”

Section: Introductionmentioning

confidence: 99%

Computational fluid dynamics investigation of thermal–hydraulic characteristics for a steam generator with and without tube support plates

Yang

Sun

et al. 2013

Proceedings of the Institution of Mechanical Engineers, Part C:

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A three-dimensional computational fluid dynamics model with the thermal phase change model is used to investigate the thermal–hydraulic characteristics of a steam generator with and without quatrefoil tube support plates. The two types of modeled designs are a unit pipe with and one without tube support plates. The computational fluid dynamics simulations capture the boiling phenomena, vortex and recirculation distributions, and the periodic characteristics of the circumferential wall temperature in the regions surrounding the tube support plates. The cross-flow energy responsible for flow-induced vibration damage in the region of the U-bend tubes is obtained with the aid of these localized thermal–hydraulic distributions. A comparison between the key parameters of the unit pipe models with and without tube support plates clearly reveals the influence of tube support plates in guiding flow behavior and alleviating flow-induced vibration damage for a steam generator’s U-bend tube bundle. Therefore, this computational fluid dynamics model can provide technical support for optimizing tube support plate design and improving the thermal–hydraulic characteristics of steam generator.

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Numerical investigation of thermal–hydraulic characteristics in a steam generator using a coupled primary and secondary side heat transfer model

Yang

Sun

2013

Annals of Nuclear Energy

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Fluidelastic instability analysis of operating nuclear steam generator U-tubes

Cited by 16 publications

References 10 publications

Analysis on the Effect of Bend Curve Radius to Inherent Characteristics of the U-Tubes

Analysis on the Effect of Bend Curve Radius to Inherent Characteristics of the U-Tubes

Computational fluid dynamics investigation of thermal–hydraulic characteristics for a steam generator with and without tube support plates

Numerical investigation of thermal–hydraulic characteristics in a steam generator using a coupled primary and secondary side heat transfer model

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