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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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RADIATION-INDUCED DISLOCATION AND GROWTH BEHAVIOR OF ZIRCONIUM AND ZIRCONIUM ALLOYS - A REVIEW

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Title
RADIATION-INDUCED DISLOCATION AND GROWTH BEHAVIOR OF ZIRCONIUM AND ZIRCONIUM ALLOYS - A REVIEW
Author
Choi, Sang IlKim, Ji Hyun
Issue Date
2013-06
Publisher
KOREAN NUCLEAR SOC
Citation
NUCLEAR ENGINEERING AND TECHNOLOGY, v.45, no.3, pp.385 - 392
Abstract
Zirconium and zirconium alloys are widely used as nuclear reactor core materials such as fuel cladding and guide tubes because they have excellent corrosion and radiation-resistant properties. In the reactor core, zirconium alloys are subjected to high-energy neutron fluence, causing radiation-induced dislocation and growth. To discern a possible correlation between radiation-induced dislocation and growth, characteristics of dislocation and growth in zirconium and its alloys are examined. The radiation-induced dislocation including and dislocation loops is reviewed in various temperature and fluence ranges, and their growth behavior is examined in the same way. To further a fundamental understanding, radiation-induced growth prediction models are briefly reviewed. This research will assist in the design of zirconium based components as well as the safety analysis of various reactor conditions, in both research and commercial reactors.
URI
https://scholarworks.unist.ac.kr/handle/201301/4044
URL
http://www.scopus.com/inward/record.url?partnerID=HzOxMe3b&scp=84879427328
DOI
10.5516/NET.07.2013.035
ISSN
1738-5733
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