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Sohn, Dong-Seong
Innovative Nuclear FUEL (INFUEL)
Research Interests
  • Nuclear fuel design

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Short communication on “self-crack-healing behavior of oxide formed on a zirconium alloy cladding tube”

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Title
Short communication on “self-crack-healing behavior of oxide formed on a zirconium alloy cladding tube”
Author
Lee, Cheol MinKim, GyeonghunSohn, Dong-SeongHan, Young-SooMok, Yong-Kyoon
Issue Date
2019-12
Publisher
Elsevier BV
Citation
JOURNAL OF NUCLEAR MATERIALS, v.526, pp.151749
Abstract
The oxidation of zirconium alloys is largely influenced by cracks in the oxide layers. It was reported that cracks formed in ZrO2/Al2O3 can be healed by the phase transformation of ZrO2. Here, we conducted several experiments to determine whether this also holds true for zirconium alloys. The experimental results showed that the cracks at the oxide-metal interface were healed after oxidation at 1200 °C, but not healed after oxidation at 1000 and 1100 °C. It appears that this crack healing behavior is related to the phase transformation of ZrO2.
URI
https://scholarworks.unist.ac.kr/handle/201301/27267
URL
https://www.sciencedirect.com/science/article/pii/S0022311519307767?via%3Dihub
DOI
10.1016/j.jnucmat.2019.151749
ISSN
0022-3115
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MNE_Journal Papers
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