Corrosion Science and Technology

  • 제2권6호
  • /
  • Pages.253-259
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  • 2003
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  • 1598-6462(pISSN)
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  • 2288-6524(eISSN)
한국부식방식학회 (The Corrosion Science Society of Korea)
권호 표지

Localized Corrosion of Pure Zr and Zircaloy-4

  • Yu, Youngran (School of Advanced Materials Science and Engineering, Andong National University) ;
  • Chang, Hyunyoung (Power Engineering Research Institute, KOPEC) ;
  • Kim, Youngsik (School of Advanced Materials Science and Engineering, Andong National University)
  • 발행 : 2003.12.01
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초록

Zirconium based alloys have been extensively used as a cladding material for fuel rods in nuclear reactors, due to their low thermal neutron absorption cross-section, excellent corrosion resistance and good mechanical properties at high temperatures. However, a cladding material for fuel rods in nuclear reactors was contact water during long time at high-temperature, so it is necessary to improve the wear and corrosion resistance of the fuel cladding, At ambient environment, there are few data or paper on the characteristic of corrosion in chloride solution and acidic solution. The specimens used in this work are pure Zr and Zircaloy-4. Zircaloy-4 is a specific zirconium-based alloy containing, on a weight percent basis, 1.4% Sn, 0.2% Fe, 0.1% Cr. Pitting corrosion resistance of two alloys by ASTM G48 is higher than that of electrochemical method. Passive film formed on Zircaloy-4 is mainly composed of $ZrO_2$, metallic Sn, and iron species regardless of formation environments. Also, passive film formed on Zr alloys shows n-type semiconductic property on the base of Mott-Schottky plot.

키워드

참고문헌

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