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손동성

Sohn, Dong-Seong
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dc.citation.endPage 352 -
dc.citation.startPage 343 -
dc.citation.title JOURNAL OF NUCLEAR MATERIALS -
dc.citation.volume 496 -
dc.contributor.author Lee, Cheol Min -
dc.contributor.author Mok, Yong-Kyoon -
dc.contributor.author Sohn, Dong-Seong -
dc.date.accessioned 2023-12-21T21:36:54Z -
dc.date.available 2023-12-21T21:36:54Z -
dc.date.created 2017-10-10 -
dc.date.issued 2017-12 -
dc.description.abstract In this study, high-temperature steam oxidation experiments were performed at 1012-1207 °C on Zr-1Nb-1Sn-0.1Fe fuel cladding tubes to study their weight gains and microstructural characteristics. Many specimens were tested at each test temperature, and the results were reproducible and reliable. It is often debated whether the Zr-1Nb-1Sn-0.1Fe alloy follows the weight gain correlation developed by Cathcart and Pawel (C-P correlation) at around 1000 °C. According to our results, the C-P correlation overpredicts the weight gain at around 1000 °C, and this observation agrees well with the data reported by Westinghouse. In addition, the microstructures of the specimens were analyzed using scanning electron microscopy, and it was found that circumferential cracks are formed at the oxide-metal interface only at around 1000 °C. In previous studies, it has been postulated that cracks in the oxide promote the oxidation process, but it appears that the circumferential cracks at the oxide-metal interface decrease the oxidation rate before the breakaway oxidation occurs by disturbing the diffusion of oxygen. The oxidation rate reduction due to the circumferential cracks appears to be the reason for the overprediction of the C-P correlation at around 1000 °C. -
dc.identifier.bibliographicCitation JOURNAL OF NUCLEAR MATERIALS, v.496, pp.343 - 352 -
dc.identifier.doi 10.1016/j.jnucmat.2017.10.013 -
dc.identifier.issn 0022-3115 -
dc.identifier.scopusid 2-s2.0-85030864306 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/22762 -
dc.identifier.url http://www.sciencedirect.com/science/article/pii/S0022311517306803 -
dc.identifier.wosid 000414205500037 -
dc.language 영어 -
dc.publisher ELSEVIER SCIENCE BV -
dc.title High-temperature steam oxidation and oxide crack effects of Zr-1Nb-1Sn-0.1Fe fuel cladding -
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.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -
dc.subject.keywordAuthor Zirconium alloy -
dc.subject.keywordAuthor Loss of coolant accident -
dc.subject.keywordAuthor Weight gain -
dc.subject.keywordAuthor Crack -
dc.subject.keywordAuthor Breakaway oxidation -
dc.subject.keywordPlus ZIRCONIUM ALLOYS -
dc.subject.keywordPlus BREAKAWAY OXIDATION -
dc.subject.keywordPlus ZIRCALOY-4 -
dc.subject.keywordPlus KINETICS -
dc.subject.keywordPlus MIXTURES -
dc.subject.keywordPlus BEHAVIOR -
dc.subject.keywordPlus REACTOR -

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