Electrochemical Characteristics of Delta Ferrite in Thermally Aged Austenitic Stainless Steel Weld

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dc.contributor.authorSubramanian, Gokul Obulanko
dc.contributor.authorHong, Sunghoonko
dc.contributor.authorLee, Ho Jungko
dc.contributor.authorKong, Byeong Seoko
dc.contributor.authorLee, Kyoung-Sooko
dc.contributor.authorByun, Thak Sangko
dc.contributor.authorJang, Changheuiko
dc.date.accessioned2020-06-23T01:20:57Z-
dc.date.available2020-06-23T01:20:57Z-
dc.date.created2020-06-11-
dc.date.issued2017-08-
dc.identifier.citation18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, pp.653 - 661-
dc.identifier.issn2367-1181-
dc.identifier.urihttp://hdl.handle.net/10203/274799-
dc.description.abstractAn austenitic stainless steel Type 316L weld was thermally aged for 20,000 h at 400 degrees C and electrochemical characterization was performed to measure corrosion resistance in delta-ferrite phase. It is well known that a severe thermal aging causes decrease of fracture resistance and increase of the hardness of delta-ferrite, which was related to the spinodal decomposition. After thermal aging, the DL-EPR response of 316L weld was dominated by parent austenite matrix without reactivation peak. To characterize the delta-ferrite only, austenite phase was selectively dissolved from the matrix by electrochemical etching method. The double-loop electrochemical potentiokinetic reactivation (DL-EPR) analysis of the delta-ferrite phase showed degradation in corrosion resistance after thermal aging with the appearance of a cathodic loop and reactivation peak during the reverse scan. The degradation in corrosion resistance of delta-ferrite phase could be attributed to the localized Cr-depletion due to spinodal decomposition and precipitation of inter-metallic phases during thermal aging.-
dc.languageEnglish-
dc.publisherSPRINGER INTERNATIONAL PUBLISHING AG-
dc.titleElectrochemical Characteristics of Delta Ferrite in Thermally Aged Austenitic Stainless Steel Weld-
dc.typeConference-
dc.identifier.wosid000456874000050-
dc.identifier.scopusid2-s2.0-85042455819-
dc.type.rimsCONF-
dc.citation.beginningpage653-
dc.citation.endingpage661-
dc.citation.publicationname18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors-
dc.identifier.conferencecountrySZ-
dc.identifier.conferencelocationPortland, OR-
dc.identifier.doi10.1007/978-3-319-68454-3_50-
dc.contributor.localauthorJang, Changheui-
dc.contributor.nonIdAuthorSubramanian, Gokul Obulan-
dc.contributor.nonIdAuthorHong, Sunghoon-
dc.contributor.nonIdAuthorLee, Ho Jung-
dc.contributor.nonIdAuthorLee, Kyoung-Soo-
dc.contributor.nonIdAuthorByun, Thak Sang-
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NE-Conference Papers(학술회의논문)
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