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김지현

Kim, Ji Hyun
UNIST Nuclear Innovative Materials Lab.
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DC Field Value Language
dc.citation.conferencePlace KO -
dc.citation.title 2017 Water Reactor Fuel Performance Meeting -
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 2023-12-19T18:11:16Z -
dc.date.available 2023-12-19T18:11:16Z -
dc.date.created 2018-01-08 -
dc.date.issued 2017-09-11 -
dc.identifier.bibliographicCitation 2017 Water Reactor Fuel Performance Meeting -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/38427 -
dc.language 영어 -
dc.publisher 한국원자력학회 -
dc.title In-situ Investigation of Oxide on Zirconium Alloy in Primary Water -
dc.type Conference Paper -
dc.date.conferenceDate 2017-09-10 -

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