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


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