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In this paper, the crud behavior of Zr-4 and N36 zirconium cladding tube were investigated under sub-cooled nucleate flow boiling conditions in a simulated PWR primary coolant for 5000 hours. The crud deposition behavior of both Zr-4 and N36 fuel cladding tube were similar. The external cladding surface of Zr-4 and N36 cladding tube had a small amount of crud due to the limited corrosion products in the coolant of the experimental apparatus. TEM analysis indicated the crud particles consisted of oxide particles of varying sizes, identified as zirconium oxide particles and Ni(Fe, Cr)2O4 spinel. After 5000 hours, the oxide film thickness of both Zr-4 and N36 zirconium alloys was approximately 5 μm, and the oxide film had undergone two transitions. Analysis of the hydrogen content in the cladding materials showed a gradual increase in hydrogen absorption with increasing corrosion time. The increase in hydride formation was relatively slow during the first 3500 h, but after 3500 h, the hydride content increased sharply. After 5000 hours, hydrides were significantly increased and interconnected throughout the cross-section, covering the entire cross-sectional area.

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Research on Crud Deposition of Zr-4 and N36 Zirconium Alloys in Simulated PWR Primary Water Chemistry

  • 会议论文

  • 发表日期：

    2026年

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  • Li Guoqing,
  • Zhou Mingyang,
  • Qiu Xi,
  • Wang Jiamei,
  • Zhu Fawen,
  • Zengping Pu

摘要

In this paper, the crud behavior of Zr-4 and N36 zirconium cladding tube were investigated under sub-cooled nucleate flow boiling conditions in a simulated PWR primary coolant for 5000 hours. The crud deposition behavior of both Zr-4 and N36 fuel cladding tube were similar. The external cladding surface of Zr-4 and N36 cladding tube had a small amount of crud due to the limited corrosion products in the coolant of the experimental apparatus. TEM analysis indicated the crud particles consisted of oxide particles of varying sizes, identified as zirconium oxide particles and Ni(Fe, Cr)2O4 spinel. After 5000 hours, the oxide film thickness of both Zr-4 and N36 zirconium alloys was approximately 5 μm, and the oxide film had undergone two transitions. Analysis of the hydrogen content in the cladding materials showed a gradual increase in hydrogen absorption with increasing corrosion time. The increase in hydride formation was relatively slow during the first 3500 h, but after 3500 h, the hydride content increased sharply. After 5000 hours, hydrides were significantly increased and interconnected throughout the cross-section, covering the entire cross-sectional area.