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- Kim, Ji Hyun
- UNIST Nuclear Innovative Materials Lab.
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| DC Field | Value | Language |
|---|---|---|
| dc.citation.endPage | 254 | - |
| dc.citation.startPage | 243 | - |
| dc.citation.title | JOURNAL OF NUCLEAR MATERIALS | - |
| dc.citation.volume | 476 | - |
| dc.contributor.author | Choi, Kyung-Joon | - |
| dc.contributor.author | Yoo, Seung Chang | - |
| dc.contributor.author | Jin, Hyung-Ha | - |
| dc.contributor.author | Kwon, Junhyun | - |
| dc.contributor.author | Choi, Min-Jae | - |
| dc.contributor.author | Hwang, Seong Sik | - |
| dc.contributor.author | Kim, Ji Hyun | - |
| dc.date.accessioned | 2023-12-21T23:36:31Z | - |
| dc.date.available | 2023-12-21T23:36:31Z | - |
| dc.date.created | 2016-05-11 | - |
| dc.date.issued | 2016-08 | - |
| dc.description.abstract | To investigate the effects of warm rolling on the crack growth of 316L austenitic stainless steel, the crack growth rate was measured and the oxide structure was characterized in high-temperature hydrogenated water. The warm-rolled specimens showed a higher crack growth rate compared to the as-received specimens because the slip bands and dislocations produced during warm rolling served as paths for corrosion and cracking. The crack growth rate increased with the dissolved hydrogen concentration. This may be attributed to the decrease in performance and stability of the protective oxide layer formed on the surface of stainless steel in high-temperature water. | - |
| dc.identifier.bibliographicCitation | JOURNAL OF NUCLEAR MATERIALS, v.476, pp.243 - 254 | - |
| dc.identifier.doi | 10.1016/j.jnucmat.2016.04.051 | - |
| dc.identifier.issn | 0022-3115 | - |
| dc.identifier.scopusid | 2-s2.0-84966269067 | - |
| dc.identifier.uri | https://scholarworks.unist.ac.kr/handle/201301/19214 | - |
| dc.identifier.url | http://www.sciencedirect.com/science/article/pii/S0022311516301738 | - |
| dc.identifier.wosid | 000377307800028 | - |
| dc.language | 영어 | - |
| dc.publisher | ELSEVIER SCIENCE BV | - |
| dc.title | Crack growth behavior of warm-rolled 316L austenitic stainless steel in high-temperature hydrogenated water | - |
| 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 | 316L stainless steel | - |
| dc.subject.keywordAuthor | Warm rolling | - |
| dc.subject.keywordAuthor | Crack growth rate measurement | - |
| dc.subject.keywordAuthor | TEM | - |
| dc.subject.keywordAuthor | Crack growth | - |
| dc.subject.keywordAuthor | Oxidation | - |
| dc.subject.keywordPlus | STRESS-CORROSION CRACKING | - |
| dc.subject.keywordPlus | PWR PRIMARY WATER | - |
| dc.subject.keywordPlus | NEUTRON-IRRADIATION | - |
| dc.subject.keywordPlus | DISSOLVED HYDROGEN | - |
| dc.subject.keywordPlus | OXIDE-FILM | - |
| dc.subject.keywordPlus | SEGREGATION | - |
| dc.subject.keywordPlus | RESISTANCE | - |
| dc.subject.keywordPlus | ALLOYS | - |
| dc.subject.keywordPlus | TIP | - |
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