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김지현

Kim, Ji Hyun
UNIST Nuclear Innovative Materials Lab.
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In-situ Investigation of Oxide on Zirconium Alloy in Primary Water

Author(s)
Kim, TaehoYoo, Seung ChangLee, YunjuKim, Ji Hyun
Issued Date
2017-09-11
URI
https://scholarworks.unist.ac.kr/handle/201301/38427
Citation
2017 Water Reactor Fuel Performance Meeting
Publisher
한국원자력학회

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