Nuclear Engineering and Technology

  • 제54권3호
  • /
  • Pages.984-990
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  • 2022
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Corrosion release behavior of alloy 690 and its application in high-temperature water with Zn injection

  • Liao, Jiapeng (China Nuclear Power Technology Research Institute) ;
  • Hu, Yousen (China Nuclear Power Technology Research Institute) ;
  • Li, Jinggang (China Nuclear Power Technology Research Institute) ;
  • Jin, Desheng (China Nuclear Power Technology Research Institute) ;
  • Meng, Shuqi (China Nuclear Power Technology Research Institute) ;
  • Ruan, Tianming (China Nuclear Power Technology Research Institute) ;
  • Hu, Yisong (China Nuclear Power Technology Research Institute) ;
  • Zhang, Ziyu (Institute of Metal Research, Chinese Academy of Sciences)
  • 투고 : 2021.05.27
  • 심사 : 2021.09.07
  • 발행 : 2022.03.25
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초록

Corrosion release behavior of Alloy 690 in high-temperature water was investigated under the conditions of injected Zn concentrations of 0 ppb, 10 ppb and 50 ppb. A protective oxide film composed of Zn(FexCr1-x)2O4 and Cr2O3 was formed with Zn injection, resulting in a better corrosion resistance. In comparison with the Zn-free condition, the corrosion release rate under the Zn-injection conditions was smaller. The corrosion release inhibiting factors were 1.7 and 1.9 under the conditions of 10 ppb and 50 ppb Zn-injection respectively. A foreseen application of the corrosion and corrosion release rates has been proposed and discussed.

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과제정보

This work was supported by the National Natural Science Foundation of China (U20B2011).

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