Please use this identifier to cite or link to this item: https://scholarbank.nus.edu.sg/handle/10635/50810
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dc.titleWeibull stress analysis for an embedded crack in reactor pressure vessels under pressurized thermal shock
dc.contributor.authorQian, X.
dc.contributor.authorDodds Jr., R.H.
dc.date.accessioned2014-04-23T08:17:19Z
dc.date.available2014-04-23T08:17:19Z
dc.date.issued2008
dc.identifier.citationQian, X.,Dodds Jr., R.H. (2008). Weibull stress analysis for an embedded crack in reactor pressure vessels under pressurized thermal shock. Key Engineering Materials 385-387 : 773-776. ScholarBank@NUS Repository.
dc.identifier.issn10139826
dc.identifier.urihttp://scholarbank.nus.edu.sg/handle/10635/50810
dc.description.abstractThis paper describes the Weibull stress approach in predicting the cumulative probability of cleavage fracture for an axially embedded crack in the wall of a reactor pressure vessel (RPV) subjected to a thermal-mechanical transient typical for an accidental, pressurized thermal shock (PTS) event. This study demonstrates the need for detailed elastic-plastic analyses in the integrity assessment of RPVs under PTS loadings, and proposes both a simplified approach and a refined approach to assess the probability of fracture for RPVs subjected to such events.
dc.sourceScopus
dc.subjectCleavage fracture
dc.subjectDuctile-to-brittle transition
dc.subjectEmbedded crack
dc.subjectPressurized thermal shock (PTS)
dc.subjectReactor pressure vessel (RPV)
dc.subjectWeibull stress
dc.typeConference Paper
dc.contributor.departmentCIVIL ENGINEERING
dc.description.sourcetitleKey Engineering Materials
dc.description.volume385-387
dc.description.page773-776
dc.description.codenKEMAE
dc.identifier.isiutNOT_IN_WOS
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