Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)

Korean Nuclear Society (한국원자력학회)
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In-pile Test Results of HANA Claddings in Halden Research Reactor

  • Baek, Jong-Hyuk (Zirconium Fuel Cladding Team, Korea Atomic Energy Research Institute) ;
  • Choi, Byoung-Kwon (Zirconium Fuel Cladding Team, Korea Atomic Energy Research Institute) ;
  • Jeong, Yong-Hwan (Zirconium Fuel Cladding Team, Korea Atomic Energy Research Institute) ;
  • Jung, Yun-Ho (Zirconium Fuel Cladding Team, Korea Atomic Energy Research Institute) ;
  • Kim, Kyu-Tae (Korea Nuclear Fuel Co., Ltd.)
  • Published : 2005.05.26
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Abstract

1. The oxide thickness on the fuelled test rods was within the following range from 7 ${\mu}m$ to 17 ${\mu}m$. In general, the HANA claddings showed better corrosion behavior than the two reference alloys (A-Cladding and Zr-4). 2. The weight gains of corrosion coupons were ranged from 21 to 56 mg/$dm^2$.

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