Title of article
Flow-inducedvibrationandfretting-wearpredictionsofsteamgeneratorhelicaltubesOriginalResearchArticle
Author/Authors
JongChullJo، نويسنده , , MyungJoJhung، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2008
Pages
14
From page
890
To page
903
Abstract
Thispaperaddressesthepotentialflow-inducedvibrationsandfretting-wearofhelicallycoiledtubesoftheonce-throughsteamgeneratoremployedatanintegraltypenuclearreactor,wherethetubesaresubjectedtoliquidcross-flowexternallyandmulti-phaseflowinternally.Thethermal-hydraulicconditionsofbothtubesideandshellsideflowfieldsarepredictedusingageneralpurposecomputationalfluiddynamicscodeusingthefinitevolumeelementmodeling.Togetthenaturalfrequencyandcorrespondingmodeshapeofthehelicallycoiledtubeswithvariousconditions,afiniteelementanalysiscodeisused.Basedontheresultsofboththethermal-hydraulicanalysisofhelicallycoiledtubesteamgeneratorandthemodalanalysisofthetubes,predictionsofturbulence-inducedvibration,fluidelasticinstabilityandfretting-wearofthehelicallycoiledtubesareperformed.Inthepredictions,specialemphasisisplacedondeterminingtheeffectsofthenumberofsupports,coildiameterandhelixpitchonthenaturalvibrationmode,turbulencevibrationamplitude,fluidelasticinstabilityandfretting-wearcharacteristicsofthetubes.Theresultsprovidethetechnicalinformationandbasesneededbydesignersandregulatoryreviewersforevaluatingthedesign.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2008
Journal title
Nuclear Engineering and Design Eslah
Record number
895053
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