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김지현

Kim, Ji Hyun
UNIST Nuclear Innovative Materials Lab.
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A study on compatibility of ferritic-martensitic steels with high- Temperature sodium for SFR application

Author(s)
Shin, SanghunKim, Ji HyunKim, Junhwan
Issued Date
2014-06-15
URI
https://scholarworks.unist.ac.kr/handle/201301/46731
Citation
2014 Annual Meeting on 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.1012 - 1015
Abstract
[No abstract available]
Publisher
2014 Annual Meeting on Transactions of the American Nuclear Society and Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NSFM 2014
ISSN
0003-018X

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