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.
Skip Nav Destination
Article navigation
October 2014
Research-Article
Evaluation of the Integrity of Steam Generator Tubes Subjected to Flow Induced Vibrations
Jovica Riznic
Jovica Riznic
Operational Engineering Assessment Division,
e-mail: jovica.riznic@cnsc-ccsn.gc.ca
Canadian Nuclear Safety Commission
,Ottawa, ON K1P 5S9
, Canada
e-mail: jovica.riznic@cnsc-ccsn.gc.ca
Search for other works by this author on:
Marwan Hassan
Jovica Riznic
Operational Engineering Assessment Division,
e-mail: jovica.riznic@cnsc-ccsn.gc.ca
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. Oct 2014, 136(5): 051301 (11 pages)
Published Online: August 19, 2014
Article history
Received:
August 29, 2013
Revision Received:
February 13, 2014
Citation
Hassan, M., and Riznic, J. (August 19, 2014). "Evaluation of the Integrity of Steam Generator Tubes Subjected to Flow Induced Vibrations." ASME. J. Pressure Vessel Technol. October 2014; 136(5): 051301. https://doi.org/10.1115/1.4026982
Download citation file:
Get Email Alerts
Latent Pitfalls in Microstructure-Based Modeling for Thermally Aged 9Cr-1Mo-V Steel (Grade 91)
J. Pressure Vessel Technol
Thermal Stress Analysis of Compact Heat Exchanger Produced by Additive Manufacturing
J. Pressure Vessel Technol
An Improved Model for Predicting Affected Region of Flashing Jet
J. Pressure Vessel Technol
Crack Growth Prediction Based on Uncertain Parameters Using Ensemble Kalman Filter
J. Pressure Vessel Technol
Related Articles
Fluidelastic Instability Modeling of Loosely Supported Multispan U-Tubes in Nuclear Steam Generators
J. Pressure Vessel Technol (February,2013)
Rotordynamic Performance of Hybrid Air Foil Bearings With Regulated Hydrostatic Injection
J. Eng. Gas Turbines Power (January,2018)
Rotordynamic Computational and Experimental Characterization of a Convergent Honeycomb Seal Tested With Negative Preswirl, High Pressure With Static Eccentricity and Angular Misalignment
J. Eng. Gas Turbines Power (May,2017)
Impact Simulation of Process Equipment Tubes and Support Plates—A Numerical Algorithm
J. Pressure Vessel Technol (February,1987)
Related Proceedings Papers
Related Chapters
Hydrodynamic Mass, Natural Frequencies and Mode Shapes
Flow-Induced Vibration Handbook for Nuclear and Process Equipment
Fluidelastic Instability of Tube Bundles in Single-Phase Flow
Flow-Induced Vibration Handbook for Nuclear and Process Equipment
Random Turbulence Excitation in Single-Phase Flow
Flow-Induced Vibration Handbook for Nuclear and Process Equipment