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- Sohn, Dong-Seong
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| DC Field | Value | Language |
|---|---|---|
| dc.citation.startPage | 151749 | - |
| dc.citation.title | JOURNAL OF NUCLEAR MATERIALS | - |
| dc.citation.volume | 526 | - |
| dc.contributor.author | Lee, Cheol Min | - |
| dc.contributor.author | Kim, Gyeonghun | - |
| dc.contributor.author | Sohn, Dong-Seong | - |
| dc.contributor.author | Han, Young-Soo | - |
| dc.contributor.author | Mok, Yong-Kyoon | - |
| dc.date.accessioned | 2023-12-21T18:17:20Z | - |
| dc.date.available | 2023-12-21T18:17:20Z | - |
| dc.date.created | 2019-08-14 | - |
| dc.date.issued | 2019-12 | - |
| dc.description.abstract | The oxidation of zirconium alloys is largely influenced by cracks in the oxide layers. It was reported that cracks formed in ZrO2/Al2O3 can be healed by the phase transformation of ZrO2. Here, we conducted several experiments to determine whether this also holds true for zirconium alloys. The experimental results showed that the cracks at the oxide-metal interface were healed after oxidation at 1200 °C, but not healed after oxidation at 1000 and 1100 °C. It appears that this crack healing behavior is related to the phase transformation of ZrO2. | - |
| dc.identifier.bibliographicCitation | JOURNAL OF NUCLEAR MATERIALS, v.526, pp.151749 | - |
| dc.identifier.doi | 10.1016/j.jnucmat.2019.151749 | - |
| dc.identifier.issn | 0022-3115 | - |
| dc.identifier.scopusid | 2-s2.0-85070870724 | - |
| dc.identifier.uri | https://scholarworks.unist.ac.kr/handle/201301/27267 | - |
| dc.identifier.url | https://www.sciencedirect.com/science/article/pii/S0022311519307767?via%3Dihub | - |
| dc.identifier.wosid | 000500777900041 | - |
| dc.language | 영어 | - |
| dc.publisher | Elsevier BV | - |
| dc.title | Short communication on “self-crack-healing behavior of oxide formed on a zirconium alloy cladding tube” | - |
| 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 | Scanning electron microscopy (SEM) | - |
| dc.subject.keywordAuthor | Crack | - |
| dc.subject.keywordAuthor | Self-crack-healing | - |
| dc.subject.keywordAuthor | Fuel cladding | - |
| dc.subject.keywordAuthor | Zirconium alloy | - |
| dc.subject.keywordAuthor | Oxidation | - |
| dc.subject.keywordAuthor | Corrosion | - |
| dc.subject.keywordPlus | ACCIDENT-TOLERANT FUEL | - |
| dc.subject.keywordPlus | HIGH-TEMPERATURE STEAM | - |
| dc.subject.keywordPlus | OXIDATION BEHAVIOR | - |
| dc.subject.keywordPlus | PREFORMED OXIDES | - |
| dc.subject.keywordPlus | PHASE | - |
| dc.subject.keywordPlus | ZIRCALOY-4 | - |
| dc.subject.keywordPlus | KINETICS | - |
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