Effects of high temperature aging in an impure helium environment on low temperature embrittlement of Alloy 617 and Haynes 230

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dc.contributor.authorKim, Daejongko
dc.contributor.authorSah, Injinko
dc.contributor.authorJang, Changheuiko
dc.date.accessioned2011-02-15-
dc.date.available2011-02-15-
dc.date.created2012-02-06-
dc.date.created2012-02-06-
dc.date.issued2010-10-
dc.identifier.citationJOURNAL OF NUCLEAR MATERIALS, v.405, no.1, pp.9 - 16-
dc.identifier.issn0022-3115-
dc.identifier.urihttp://hdl.handle.net/10203/22140-
dc.description.abstractThe effects of high temperature environmental damage on low temperature embrittlement of wrought nickel-base superalloys, Alloy 617 and Haynes 230 were evaluated. They were aged in an impure helium environment at 1000 degrees C for up to 500 h before tensile tested at room temperature. The tensile test results showed that the loss of ductility was associated with the increase in the inter-granular fracture with aging time. For Alloy 617, inter-granular oxidation and coarsening of grain boundary carbides contributed to the embrittlement. The significant loss of ductility in Haynes 230 was only observed after 500 h of aging when the globular intermetallic precipitates were extensively formed and brittle inter-granular cracking began to occur. (C) 2010 Elsevier B.V. All rights reserved.-
dc.description.sponsorshipThis work was supported by the MEST / NRF (Nuclear R&D Program, 2005-2004718 and 2009-0083392) of Korea. Part of the funding was provided by the Second Phase BK21 Program of the Ministry of Education, Science and Technology of Korea.en
dc.languageEnglish-
dc.language.isoen_USen
dc.publisherELSEVIER SCIENCE BV-
dc.subjectMETALLIC MATERIALS-
dc.subjectCORROSION-
dc.titleEffects of high temperature aging in an impure helium environment on low temperature embrittlement of Alloy 617 and Haynes 230-
dc.typeArticle-
dc.identifier.wosid000282398000002-
dc.identifier.scopusid2-s2.0-77956193944-
dc.type.rimsART-
dc.citation.volume405-
dc.citation.issue1-
dc.citation.beginningpage9-
dc.citation.endingpage16-
dc.citation.publicationnameJOURNAL OF NUCLEAR MATERIALS-
dc.identifier.doi10.1016/j.jnucmat.2010.07.026-
dc.embargo.liftdate9999-12-31-
dc.embargo.terms9999-12-31-
dc.contributor.localauthorJang, Changheui-
dc.type.journalArticleArticle-
dc.subject.keywordPlusMETALLIC MATERIALS-
dc.subject.keywordPlusCORROSION-
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