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Park, Sang-Yoon;Choi, Byoung-Kown;Choi, Byung-Seon;Yoon, Ju-Hyeon;Lee, Doo-Jeong;Jeong, Young-Hwan
- Proceedings of the Korean Nuclear Society Conference
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- 2005.10a
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- pp.340-341
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- 2005
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Choi, Sang Il;Kim, Ji Hyun
- Nuclear Engineering and Technology
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- v.45 no.3
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- pp.385-392
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- 2013
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.

Park, Jeong-Yong;Park, Sang-Yun;Lee, Myung-Ho;Choi, Byung-Kwon;Baek, Jong-Hyuk;Kim, Jun-Hwan;Kim, Hyun-Gil;Jeong, Yong-Hwan;Kim, Gyu-Tae;Jung, Youn-Ho
- Proceedings of the Korean Nuclear Society Conference
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- 2005.05a
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- pp.423-424
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- 2005
The performance of HANA claddings was evaluated in out-of-pile conditions. All the performance test results revealed that HANA claddings were superior to the reference claddings such as Zircaloy-4 and A-cladding. Corrosion resistance was improved by 60 to 70% compared to the commercial claddings. Creep, burst, tensile, LOCA, wear and microstructural properties were shown to be as good as the commercial claddings.
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