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- Kim, Ji Hyun
- UNIST Nuclear Innovative Materials Lab.
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| DC Field | Value | Language |
|---|---|---|
| dc.citation.conferencePlace | CC | - |
| dc.citation.title | Symposium on Water Chemistry and Corrosion in Nuclear Power plants in Asia-2017 & 6th International Symposium on Materials and Reliability in Nuclear Power Plants | - |
| dc.contributor.author | Kim, Taeho | - |
| dc.contributor.author | Yoo, Seung Chang | - |
| dc.contributor.author | Lee, Yunju | - |
| dc.contributor.author | Kim, Ji Hyun | - |
| dc.date.accessioned | 2023-12-19T18:10:00Z | - |
| dc.date.available | 2023-12-19T18:10:00Z | - |
| dc.date.created | 2018-01-08 | - |
| dc.date.issued | 2017-09-27 | - |
| dc.identifier.bibliographicCitation | Symposium on Water Chemistry and Corrosion in Nuclear Power plants in Asia-2017 & 6th International Symposium on Materials and Reliability in Nuclear Power Plants | - |
| dc.identifier.uri | https://scholarworks.unist.ac.kr/handle/201301/38424 | - |
| dc.language | 영어 | - |
| dc.publisher | China Nuclear Energy Association | - |
| dc.title | In-situ Investigation of Zirconium Oxide Alloy in Primary Water with Different Dissolved Hydrogen Concentration | - |
| dc.type | Conference Paper | - |
| dc.date.conferenceDate | 2017-09-26 | - |
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