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김지현

Kim, Ji Hyun
UNIST Nuclear Innovative Materials Lab.
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Modeling irradiation growth of zirconium and its alloy in nuclear reactors

Author(s)
Choi, SangKim, TaehoShin, SanghunLee, GyeonggeunKwon, JunhyunKim, Ji Hyun
Issued Date
2014-06-15
URI
https://scholarworks.unist.ac.kr/handle/201301/47043
Citation
2014 Annual Meeting - Transactions of the American Nuclear Society and Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NSFM 2014, v.110, pp.877 - 879
Publisher
American Nuclear Society
ISSN
0003-018X

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