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http://dx.doi.org/10.5516/NET.07.2013.035

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

Choi, Sang Il (Interdisciplinary School of Green Energy Ulsan National Institute of Science and Technology (UNIST))
Kim, Ji Hyun (Interdisciplinary School of Green Energy Ulsan National Institute of Science and Technology (UNIST))
Publication Information
Nuclear Engineering and Technology / v.45, no.3, 2013 , pp. 385-392 More about this Journal
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.
Keywords
Zirconium; Zircaloy; Radiation-induced Dislocation; Radiation-induced Growth; Radiation Damage Theory;
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