Role of residual ferrites on crevice SCC of austenitic stainless steels in PWR water with high-dissolved oxygen

Cited 2 time in webofscience Cited 1 time in scopus
  • Hit : 361
  • Download : 0
DC FieldValueLanguage
dc.contributor.authorSinjlawi, Abdullahko
dc.contributor.authorChen, Junjieko
dc.contributor.authorKim, Ho-Subko
dc.contributor.authorLee, Hyeon Baeko
dc.contributor.authorJang, Changheuiko
dc.contributor.authorLee, Sanghoonko
dc.date.accessioned2020-10-13T08:55:14Z-
dc.date.available2020-10-13T08:55:14Z-
dc.date.created2020-06-26-
dc.date.created2020-06-26-
dc.date.issued2020-11-
dc.identifier.citationNUCLEAR ENGINEERING AND TECHNOLOGY, v.52, no.11, pp.2552 - 2564-
dc.identifier.issn1738-5733-
dc.identifier.urihttp://hdl.handle.net/10203/276535-
dc.description.abstractThe crevice stress corrosion cracking (SCC) susceptibility of austenitic stainless steels was evaluated in simulated pressurized water reactor (PWR) environments. To simulate the abnormal condition in temporary clamping devices on leaking small bore pipes, crevice bent beam (CBB) tests were performed in the oxygenated as well as hydrogenated conditions. No SCC cracks were found for SS316 in both conditions. SS304 also showed good resistance in the hydrogenated condition. However, all SS304 specimens showed SCC cracks in the oxygenated condition, indicating poor crevice SCC resistance. It was found that residual ferrites were selectively dissolved because of the galvanic corrosion coupled with the neighbouring austenite phase, resulting in SCC initiation in SS304. Crack morphologies were mostly transgranular assisted by the damaged delta-ferrite and deformation-induced slip bands.-
dc.languageEnglish-
dc.publisherKOREAN NUCLEAR SOC-
dc.titleRole of residual ferrites on crevice SCC of austenitic stainless steels in PWR water with high-dissolved oxygen-
dc.typeArticle-
dc.identifier.wosid000567837900001-
dc.identifier.scopusid2-s2.0-85084410863-
dc.type.rimsART-
dc.citation.volume52-
dc.citation.issue11-
dc.citation.beginningpage2552-
dc.citation.endingpage2564-
dc.citation.publicationnameNUCLEAR ENGINEERING AND TECHNOLOGY-
dc.identifier.doi10.1016/j.net.2020.04.023-
dc.contributor.localauthorJang, Changheui-
dc.contributor.nonIdAuthorSinjlawi, Abdullah-
dc.contributor.nonIdAuthorChen, Junjie-
dc.contributor.nonIdAuthorLee, Sanghoon-
dc.description.isOpenAccessY-
dc.type.journalArticleArticle-
dc.subject.keywordAuthorResidual delta-ferrite-
dc.subject.keywordAuthorAustenitic stainless steel-
dc.subject.keywordAuthorCrevice beam bent (CBB)-
dc.subject.keywordAuthorStress corrosion cracking (SCC)-
dc.subject.keywordPlusSTRESS-CORROSION CRACKING-
dc.subject.keywordPlusOXIDATION BEHAVIOR-
dc.subject.keywordPlusCOLD WORK-
dc.subject.keywordPlusSUSCEPTIBILITY-
dc.subject.keywordPlus304-STAINLESS-STEEL-
dc.subject.keywordPlusSENSITIZATION-
dc.subject.keywordPlusDIAGRAMS-
Appears in Collection
NE-Journal Papers(저널논문)
Files in This Item
There are no files associated with this item.
This item is cited by other documents in WoS
⊙ Detail Information in WoSⓡ Click to see webofscience_button
⊙ Cited 2 items in WoS Click to see citing articles in records_button

qr_code

  • mendeley

    citeulike


rss_1.0 rss_2.0 atom_1.0