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Kim, Ji Hyun
UNIST Nuclear Innovative Materials Laboratory(UNIMAT)
Research Interests
  • High temperature water corrosion
  • Liquid metal corrosion
  • Material degradation simulation

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Modeling of radiation-induced sink evolution in 6061 aluminum alloy in nuclear reactors

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Title
Modeling of radiation-induced sink evolution in 6061 aluminum alloy in nuclear reactors
Author
Choi, Sang IlLee, Gyeong-GeunKwon, JunhyunKim, Ji Hyun
Issue Date
2016-11
Publisher
WILEY-V C H VERLAG GMBH
Citation
PHYSICA STATUS SOLIDI A-APPLICATIONS AND MATERIALS SCIENCE, v.213, no.11, pp.3000 - 3006
Abstract
The objective of this study is a detailed analysis of the radiation effects on sink generation and growth in order to understand the phenomenon of irradiation hardening of 6061 aluminum alloy in research reactor conditions. In order to have a fundamental understanding, various sink behavior characteristics such as size and number density of dislocation loop, void, and precipitation were calculated and examined. Thereafter, theoretical assessment of various sink effects on irradiation hardening was conducted based on the mean field rate theory (MFRT). Dislocation loop, void, and precipitation were examined by defect flux. For the quantitative analysis of radiation-induced degradation, change in sink size was calculated using number density. 6061 Alloy showed great dependence on precipitation generation and growth. However, dislocation loop and void did not have any significant effect on irradiation hardening. Finally, the behavior of sinks was compared with the experimental results for validation.
URI
https://scholarworks.unist.ac.kr/handle/201301/20748
URL
http://onlinelibrary.wiley.com/doi/10.1002/pssa.201600124/abstract
DOI
10.1002/pssa.201600124
ISSN
1862-6300
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