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Volume 38 Issue S1
Feb.  2025
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Wang Huacai, Tang Qi, Fu Cheng, Liang Zhengqiang. Raman Spectroscopy Analysis of Oxide Film Formed on Cladding of Spent Fuel Rod from Nuclear Power Plants[J]. Nuclear Power Engineering, 2017, 38(S1): 110-114. doi: 10.13832/j.jnpe.2017.S1.0110
Citation: Wang Huacai, Tang Qi, Fu Cheng, Liang Zhengqiang. Raman Spectroscopy Analysis of Oxide Film Formed on Cladding of Spent Fuel Rod from Nuclear Power Plants[J]. Nuclear Power Engineering, 2017, 38(S1): 110-114. doi: 10.13832/j.jnpe.2017.S1.0110

Raman Spectroscopy Analysis of Oxide Film Formed on Cladding of Spent Fuel Rod from Nuclear Power Plants

doi: 10.13832/j.jnpe.2017.S1.0110
  • Received Date: 2016-09-30
  • Rev Recd Date: 2017-05-23
  • Available Online: 2025-02-09
  • The crystal structure of the oxide film of Zr-4 alloy of different positions from the bottom of fuel rod, which comes from Qinshan nuclear power plant phase 1, is investigated by Raman spectroscopy method. The results indicate that the bottom of the rod has better corrosion resistance and more tetragonal ZrO2, and has the black appearance which is compact. With the increasing of the distance from the bottom, the corrosion is more and more severe, the average content of tetragonal ZrO2 in the oxide film decreases, that of monoclinic ZrO2 increases, and tetragonal ZrO2 transforms into monoclinic ZrO2, and there is a gradual transition from the black and white appearance into white and porous appearance. In the cross section, from the oxide/metal interface to the surface of the oxide film, the content of tetragonal ZrO2 reduces gradually and the monoclinic ZrO2 increases. The result is similar to the investigations in the autoclave, i.e., the transformation from tetragonal ZrO2 to monoclinic ZrO2 decides the corrosion resistance of Zr-4 alloy in the reactor, and the higher the m-ZrO2 content in the oxide film is, the higher corrosion rate of cladding, and the worse corrosion resistance property.

     

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