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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.title | Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2018) | - |
| dc.contributor.author | Kim, Taeho | - |
| dc.contributor.author | Kim, Seunghyun | - |
| dc.contributor.author | Lee, Yunju | - |
| dc.contributor.author | Ham, Junhyuk | - |
| dc.contributor.author | Kim, Ji Hyun | - |
| dc.date.accessioned | 2023-12-19T15:48:01Z | - |
| dc.date.available | 2023-12-19T15:48:01Z | - |
| dc.date.created | 2019-01-07 | - |
| dc.date.issued | 2018-06-17 | - |
| dc.identifier.bibliographicCitation | Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2018) | - |
| dc.identifier.uri | https://scholarworks.unist.ac.kr/handle/201301/36412 | - |
| dc.language | 영어 | - |
| dc.publisher | American Nuclear Society | - |
| dc.title | Electronic Structure and Hybridization Effects of Zirconium Alloy in High Temperature Water | - |
| dc.type | Conference Paper | - |
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