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방인철

Bang, In Cheol
Nuclear Thermal Hydraulics and Reactor Safety Lab.
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dc.citation.endPage 102 -
dc.citation.number 1-3 -
dc.citation.startPage 92 -
dc.citation.title JOURNAL OF NUCLEAR MATERIALS -
dc.citation.volume 422 -
dc.contributor.author Shin, Sang Hun -
dc.contributor.author Kim, Jong Jin -
dc.contributor.author Jung, Ju Ang -
dc.contributor.author Choi, Kyoung Joon -
dc.contributor.author Bang, In Cheol -
dc.contributor.author Kim, Ji Hyun -
dc.date.accessioned 2023-12-22T05:17:10Z -
dc.date.available 2023-12-22T05:17:10Z -
dc.date.created 2013-06-07 -
dc.date.issued 2012-03 -
dc.description.abstract The purpose of this study is to investigate the interaction between austenitic stainless steel, AISI 316L, and gallium liquid metal at a high temperature, for the potential application to advanced fast reactor coolants. Test specimens of AISI 316L were exposed to static gallium at 500 degrees C for up to 700 h in two different cover-gas conditions, including air and vacuum. Similar experimental tests were conducted in gallium alloy liquid metal environments, including Ga-14Sn-6Zn and Ga-8Sn-6Zn, in order to study the effect of addition of alloying elements. The results have shown that the weight change and metal loss of specimens were generally reduced in Ga-14Sn-6Zn and Ga-8Sn-6Zn compared to those in pure gallium at a high temperature. -
dc.identifier.bibliographicCitation JOURNAL OF NUCLEAR MATERIALS, v.422, no.1-3, pp.92 - 102 -
dc.identifier.doi 10.1016/j.jnucmat.2011.12.007 -
dc.identifier.issn 0022-3115 -
dc.identifier.scopusid 2-s2.0-84862795711 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/3000 -
dc.identifier.url http://www.scopus.com/inward/record.url?partnerID=HzOxMe3b&scp=84862795711 -
dc.identifier.wosid 000301563200012 -
dc.language 영어 -
dc.publisher ELSEVIER SCIENCE BV -
dc.title A study on corrosion behavior of austenitic stainless steel in liquid metals at high temperature -
dc.type Article -
dc.relation.journalWebOfScienceCategory Materials Science, Multidisciplinary; Nuclear Science & Technology -
dc.relation.journalResearchArea Materials Science; Nuclear Science & Technology -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -
dc.subject.keywordPlus GALLIUM -
dc.subject.keywordPlus ALLOYS -
dc.subject.keywordPlus ZINC -
dc.subject.keywordPlus DISSOLUTION -
dc.subject.keywordPlus DIFFUSION -
dc.subject.keywordPlus NICKEL -
dc.subject.keywordPlus MELTS -
dc.subject.keywordPlus IRON -
dc.subject.keywordPlus TIN -

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