Corrosion characteristics of Ni-base superalloys in high temperature steam with and without hydrogen

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dc.contributor.authorKim, Donghoonko
dc.contributor.authorKim, Daejongko
dc.contributor.authorLee, Ho Jungko
dc.contributor.authorJang, Changheuiko
dc.contributor.authorYoon, Duk Jooko
dc.date.accessioned2014-08-28T08:32:16Z-
dc.date.available2014-08-28T08:32:16Z-
dc.date.created2013-11-11-
dc.date.created2013-11-11-
dc.date.issued2013-10-
dc.identifier.citationJOURNAL OF NUCLEAR MATERIALS, v.441, no.1-3, pp.612 - 622-
dc.identifier.issn0022-3115-
dc.identifier.urihttp://hdl.handle.net/10203/188547-
dc.description.abstractThe hot steam corrosion behavior of Alloy 617 and Haynes 230 were evaluated in corrosion tests performed at 900 degrees C in steam and steam + 20 vol.% H-2 environments. Corrosion rates of Alloy 617 was faster than that of Haynes 230 at 900 degrees C in steam and steam + 20 vol.% H-2 environments. When hydrogen was added to steam, the corrosion rate was accelerated because added hydrogen increased the concentration of Cr interstitial defects in the oxide layer. Isolated nodular MnTiO3 oxides were formed on the MnCr2O4/Cr2O3 oxide layer and sub-layer Cr2O3 was formed in steam and steam + 20 vol.% H-2 for Alloy 617. On the other hand, a MnCr2O4 layer was formed on top of the Cr2O3 oxide layer for Haynes 230. The extensive sub-layer Cr2O3 formation resulted from the oxygen or hydroxide inward diffusion in such environments. When hydrogen was added, the initial surface oxide morphology was changed from a convex shape to platelets because of the accelerated diffusion of cations under the oxide layer. (C) 2013 Elsevier B.V. All rights reserved.-
dc.languageEnglish-
dc.publisherELSEVIER SCIENCE BV-
dc.subjectWATER-VAPOR-
dc.subjectHAYNES 230-
dc.subjectALLOY 617-
dc.subjectOXIDATION-
dc.subjectGROWTH-
dc.subjectDIFFUSION-
dc.subjectPRESSURE-
dc.subjectCHROMIUM-
dc.subjectBEHAVIOR-
dc.subjectOXIDES-
dc.titleCorrosion characteristics of Ni-base superalloys in high temperature steam with and without hydrogen-
dc.typeArticle-
dc.identifier.wosid000325447600079-
dc.identifier.scopusid2-s2.0-84885188277-
dc.type.rimsART-
dc.citation.volume441-
dc.citation.issue1-3-
dc.citation.beginningpage612-
dc.citation.endingpage622-
dc.citation.publicationnameJOURNAL OF NUCLEAR MATERIALS-
dc.identifier.doi10.1016/j.jnucmat.2013.04.023-
dc.embargo.liftdate9999-12-31-
dc.embargo.terms9999-12-31-
dc.contributor.localauthorJang, Changheui-
dc.contributor.nonIdAuthorKim, Donghoon-
dc.contributor.nonIdAuthorKim, Daejong-
dc.contributor.nonIdAuthorLee, Ho Jung-
dc.contributor.nonIdAuthorYoon, Duk Joo-
dc.type.journalArticleArticle; Proceedings Paper-
dc.subject.keywordPlusWATER-VAPOR-
dc.subject.keywordPlusHAYNES 230-
dc.subject.keywordPlusALLOY 617-
dc.subject.keywordPlusOXIDATION-
dc.subject.keywordPlusGROWTH-
dc.subject.keywordPlusDIFFUSION-
dc.subject.keywordPlusPRESSURE-
dc.subject.keywordPlusCHROMIUM-
dc.subject.keywordPlusBEHAVIOR-
dc.subject.keywordPlusOXIDES-
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