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contributor authorBlevins, R. D.
date accessioned2019-02-28T11:06:34Z
date available2019-02-28T11:06:34Z
date copyright4/5/2018 12:00:00 AM
date issued2018
identifier issn0094-9930
identifier otherpvt_140_03_034502.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252769
description abstractFlow-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.
publisherThe American Society of Mechanical Engineers (ASME)
titleNonproprietary Flow-Induced Vibration Analysis of San Onofre Nuclear Generating Station Replacement Steam Generators to ASME Code Section III Appendix N
typeJournal Paper
journal volume140
journal issue3
journal titleJournal of Pressure Vessel Technology
identifier doi10.1115/1.4039391
journal fristpage34502
journal lastpage034502-5
treeJournal of Pressure Vessel Technology:;2018:;volume( 140 ):;issue: 003
contenttypeFulltext


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