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김지현

Kim, Ji Hyun
UNIST Nuclear Innovative Materials Lab.
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dc.citation.endPage 210 -
dc.citation.number 3 -
dc.citation.startPage 205 -
dc.citation.title JOURNAL OF NUCLEAR MATERIALS -
dc.citation.volume 407 -
dc.contributor.author Lim, Jun -
dc.contributor.author Nam, Hyo On -
dc.contributor.author Hwang, Il Soon -
dc.contributor.author Kim, Ji Hyun -
dc.date.accessioned 2023-12-22T06:39:38Z -
dc.date.available 2023-12-22T06:39:38Z -
dc.date.created 2013-06-07 -
dc.date.issued 2010-12 -
dc.description.abstract Lead and lead bismuth eutectic (LBE) alloy have been increasingly receiving attention as heavy liquid metal coolants (HLMC) for future nuclear energy systems. The compatibility of structural materials and components with lead bismuth eutectic liquid at high temperature is one of key issues for the commercialization of lead fast reactors. In the present study, the corrosion behaviors of iron-based alumina-forming alloys (Kanthal-AF (R), PM2000, MA956) were investigated by exposing to stagnant LBE environments at 500 degrees C and 550 degrees C for up to 500 h. After exposures, the thickness and chemistry of the oxide layer on the specimens were analyzed by scanning electron microscopy, scanning transmission electron microscopy and energy dispersive X-ray spectroscopy. As a result, the oxide characteristics and the corrosion resistance were compared. In this study, it was shown that the corrosion resistance of FeCrAl ODS steels (PM2000, MA956) are superior to that of FeCrAl ferritic steel (Kanthal-AF (R)) in higher temperature LBE. -
dc.identifier.bibliographicCitation JOURNAL OF NUCLEAR MATERIALS, v.407, no.3, pp.205 - 210 -
dc.identifier.doi 10.1016/j.jnucmat.2010.10.018 -
dc.identifier.issn 0022-3115 -
dc.identifier.scopusid 2-s2.0-78649457136 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/3731 -
dc.identifier.url http://www.scopus.com/inward/record.url?partnerID=HzOxMe3b&scp=78649457136 -
dc.identifier.wosid 000285859200011 -
dc.language 영어 -
dc.publisher ELSEVIER SCIENCE BV -
dc.title A study of early corrosion behaviors of FeCrAl alloys in liquid lead-bismuth eutectic environments -
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 -

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