Flow-induced vibration analysis of the San Onofre Nuclear Generating Station (SONGS) replacement steam generators (RSG) is made using nonproprietary public data for these steam generators on the Nuclear Regulatory Commission public web site (www.NRC.gov). The analysis uses the methodology of Appendix N Section III of the ASME Boiler and Pressure Vessel Code, Subarticle N-1300 Flow-Induced Vibration of Tubes and Tube Banks. First, the tube geometry is assembled, and overall flow and performance parameters are developed at 100% design flow; then, the analysis is made to determine the flow velocity in the gap between tubes and tube natural frequencies and mode shapes. Finally, the mass damping and reduced velocity for tubes on the U bend are assembled and plotted on the ASME code Figure N-11331-4 fluid elastic stability diagram.
Nonproprietary Flow-Induced Vibration Analysis of San Onofre Nuclear Generating Station Replacement Steam Generators to ASME Code Section III Appendix N
Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received August 14, 2017; final manuscript received January 25, 2018; published online April 5, 2018. Assoc. Editor: Tomomichi Nakamura.
- Views Icon Views
- Share Icon Share
- Cite Icon Cite
- Search Site
Blevins, R. D. (April 5, 2018). "Nonproprietary Flow-Induced Vibration Analysis of San Onofre Nuclear Generating Station Replacement Steam Generators to ASME Code Section III Appendix N." ASME. J. Pressure Vessel Technol. June 2018; 140(3): 034502. https://doi.org/10.1115/1.4039391
Download citation file:
- Ris (Zotero)
- Reference Manager