Title of article
LeakbehaviorofSCCdegradedsteamgeneratortubingsofnuclearpowerplantOriginalResearchArticle
Author/Authors
SeongSikHwang، نويسنده , , HongPyoKim، نويسنده , , JoungSooKim، نويسنده , , KennethE.Kasza، نويسنده , , JangyulPark، نويسنده , , WilliamJ.Shack، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2005
Pages
8
From page
2477
To page
2484
Abstract
AforcedoutageduetoasteamgeneratortubeleakinaKoreannuclearpowerplanthasbeenreported.Primarywaterstresscorrosioncrackinghasoccurredinmanytubesintheplant,andtheywererepairedusingsleevesorplugs.Inordertodevelopproperrepaircriteria,itisnecessarytounderstandtheleakbehaviorofthetubescontainingstresscorrosioncracks.Crackedspecimenswerepreparedusingaroomtemperaturecrackingtechnique,andtheleakratesandburstpressuresofthedegradedtubesweredeterminedbothatroomtemperatureandatahightemperature.Sometubeswith100%throughwallcracksdidnotshowaleakageat10.8MPa,whichisthetypicalpressuredifferenceofthepressurizedwaterreactors(PWRs)duringanormaloperation.Insometests,theleakratesofthetubesincreasedwithtimeataconstantpressure.Inahightemperaturepressuretestat282°Conespecimenshowedaverysmallleakageat18.6MPa,whichstoppedafterasmallincreaseinthetestpressure.Becausestresscorrosioncrackscandevelopatrelativelylowstresses,even100%throughwallcrackscanbesotightthattheywillnotleakatanormaloperatingpressure.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2005
Journal title
Nuclear Engineering and Design Eslah
Record number
895957
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