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김지현

Kim, Ji Hyun
UNIST Nuclear Innovative Materials Lab.
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dc.citation.startPage 154220 -
dc.citation.title JOURNAL OF NUCLEAR MATERIALS -
dc.citation.volume 574 -
dc.contributor.author Kim, Sungyu -
dc.contributor.author Lee, Chang-Hoon -
dc.contributor.author Jang, Jae Hoon -
dc.contributor.author Moon, Joonho -
dc.contributor.author Kim, Ji Hyun -
dc.contributor.author Bahn, Chi Bum -
dc.date.accessioned 2023-12-21T13:07:17Z -
dc.date.available 2023-12-21T13:07:17Z -
dc.date.created 2023-02-17 -
dc.date.issued 2023-02 -
dc.description.abstract High-temperature steam oxidation testing is conducted at 1200 and 1300 degrees C to evaluate the oxidation resistance and characterize the oxide of the (Ti, Mo)C-forming FeCrAlY alloy developed as a candidate for accident-tolerant fuel-cladding materials in nuclear power plants. The oxidation behavior on both tem-peratures was investigated using X-ray diffraction, scanning, and transmission electron microscopies. The oxidation behavior of the new alloy indicates a temperature dependency: at 1200 degrees C, TiO2 and Y2Ti2O7 are seen on the outermost oxide layer, whereas no Ti-rich oxide is detected at 1300 degrees C, but and Y3Al5O12 are observed, which are typical oxides in carbide-free FeCrAlY alloys. On the TiO2 surface, water molecules can become dissociated, and the products of the dissociation can create more oxygen vacancies, which in turn can lead to a porous oxide layer with voids and a higher oxidation rate when compared with FeCrAlY alloys. However, at 1300 degrees C, Ti diffusion is efficiently blocked by Y segregation along oxide grain boundaries due to larger oxide grains and less intersections between the oxide grain boundaries and the oxide/metal interface. The oxidation resistance of (Ti, Mo)C-forming FeCrAlY is superior to that of the Zr alloy, which makes it a suitable candidate for accident-tolerant fuel-cladding materials from the perspec-tive of high-temperature steam oxidation.(c) 2022 Elsevier B.V. All rights reserved. -
dc.identifier.bibliographicCitation JOURNAL OF NUCLEAR MATERIALS, v.574, pp.154220 -
dc.identifier.doi 10.1016/j.jnucmat.2022.154220 -
dc.identifier.issn 0022-3115 -
dc.identifier.scopusid 2-s2.0-85145257181 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/61989 -
dc.identifier.wosid 000916426500001 -
dc.language 영어 -
dc.publisher ELSEVIER -
dc.title High-temperature steam oxidation of (Ti, Mo)C-forming FeCrAlY alloy -
dc.type Article -
dc.description.isOpenAccess FALSE -
dc.relation.journalWebOfScienceCategory Materials Science, Multidisciplinary; Nuclear Science & Technology -
dc.relation.journalResearchArea Materials Science; Nuclear Science & Technology -
dc.type.docType Article -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -
dc.subject.keywordAuthor FeCrAl -
dc.subject.keywordAuthor High-temperature steam oxidation -
dc.subject.keywordAuthor Titanium oxide -
dc.subject.keywordAuthor Porous oxide -
dc.subject.keywordPlus DEGREES-C -
dc.subject.keywordPlus BEHAVIOR -
dc.subject.keywordPlus TI2ALC -
dc.subject.keywordPlus MORPHOLOGY -
dc.subject.keywordPlus TITANIUM -
dc.subject.keywordPlus AIR -

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