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- Kim, Ji Hyun
- UNIST Nuclear Innovative Materials Lab.
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In-situ Investigation of Zirconium Oxide Alloy in Primary Water with Different Dissolved Hydrogen Concentration
- Author(s)
- Kim, Taeho, Yoo, Seung Chang, Lee, Yunju, Kim, Ji Hyun
- Issued Date
- 2017-09-27
- Citation
- Symposium on Water Chemistry and Corrosion in Nuclear Power plants in Asia-2017 & 6th International Symposium on Materials and Reliability in Nuclear Power Plants
- Publisher
- China Nuclear Energy Association
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