Corrosion Resistance of Zr–0.8Sn–0.25Nb–0.35Fe–0.1Cr–0.05Ge Alloy

  • Zhongbo Yang
  • Zongpei Wu
  • Shaoyu Qiu
  • Zhuqing Cheng
  • Jun Qiu
  • Ben Wang
  • Gaihuan Yuan
Conference paper
Part of the Springer Proceedings in Energy book series (SPE)

Abstract

The samples of Zr–0.8Sn–0.25Nb–0.35Fe–0.1Cr–0.05Ge alloy, including stress relieving annealing (SRA) and recrystallization annealing (RXA) cladding tubes, were tested in static autoclave in 360 ℃/18.6 MPa pure water, 360 ℃/18.6 MPa/0.01 mol/L LiOH aqueous solutions and 400 ℃/10.3 MPa steam. The microstructure characteristics were analyzed by Transmission Electron Microscope (TEM) and Scanning Electron Microscope (SEM). It was shown that the corrosion weight gain of RXA tube was lower than that of SRA tube in three different corrosive mediums. The fine precipitates in the alloys were mainly HCP-Zr (Nb, Fe, Cr)2 and FCC-Zr2 (Fe, Cr), which were homogeneous and dispersed. In the SRA tube, the average diameter of precipitates was relatively smaller, and a small amount of TET-Zr3Ge was also observed. The cracks paralleling to the interface of oxide/metal were formed in the fracture surface of the oxide film, and the oxide film in the inner surface presented the “Cauliflower-like” morphology. As the corrosion time increased, there were more pores or cracks in the oxide film and the size of “Cauliflower-like” structure grew bigger.

Keywords

Zr–0.8sn–0.25Nb–0.35Fe–0.1Cr-0.05Ge alloy Corrosion Microstructure Oxide films 

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Copyright information

© Springer Nature Singapore Pte Ltd. 2018

Authors and Affiliations

  • Zhongbo Yang
    • 1
  • Zongpei Wu
    • 1
  • Shaoyu Qiu
    • 1
  • Zhuqing Cheng
    • 1
  • Jun Qiu
    • 1
  • Ben Wang
    • 2
  • Gaihuan Yuan
    • 2
  1. 1.Science and Technology on Reactor Fuel and Materials LaboratoryNuclear Power Institute of ChinaChengduChina
  2. 2.State Nuclear Baoti Zirconium Industry CompanyBaojiChina

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