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- Kim, Ji Hyun
- UNIST Nuclear Innovative Materials Lab.
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| DC Field | Value | Language |
|---|---|---|
| dc.citation.conferencePlace | US | - |
| dc.citation.conferencePlace | Reno, NV; United States | - |
| dc.citation.endPage | 879 | - |
| dc.citation.startPage | 877 | - |
| dc.citation.title | 2014 Annual Meeting - Transactions of the American Nuclear Society and Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NSFM 2014 | - |
| dc.citation.volume | 110 | - |
| dc.contributor.author | Choi, Sang | - |
| dc.contributor.author | Kim, Taeho | - |
| dc.contributor.author | Shin, Sanghun | - |
| dc.contributor.author | Lee, Gyeonggeun | - |
| dc.contributor.author | Kwon, Junhyun | - |
| dc.contributor.author | Kim, Ji Hyun | - |
| dc.date.accessioned | 2023-12-20T00:06:04Z | - |
| dc.date.available | 2023-12-20T00:06:04Z | - |
| dc.date.created | 2014-09-17 | - |
| dc.date.issued | 2014-06-15 | - |
| dc.identifier.bibliographicCitation | 2014 Annual Meeting - Transactions of the American Nuclear Society and Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NSFM 2014, v.110, pp.877 - 879 | - |
| dc.identifier.issn | 0003-018X | - |
| dc.identifier.scopusid | 2-s2.0-84904613326 | - |
| dc.identifier.uri | https://scholarworks.unist.ac.kr/handle/201301/47043 | - |
| dc.language | 영어 | - |
| dc.publisher | American Nuclear Society | - |
| dc.title | Modeling irradiation growth of zirconium and its alloy in nuclear reactors | - |
| dc.type | Conference Paper | - |
| dc.date.conferenceDate | 2014-06-15 | - |
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