Impact of Impurity Ions in Secondary Circuit Water on Cracking Behaviour of PWR Steam Generator 690TT Tube

Abstract The impact of impurity ions on stress corrosion cracking (SCC) sensitivity of steam generator heat-exchange tube material Alloy 690TT in secondary circuit water (SCW) was studied at 285 °C. The pH of the test solution was adjusted using ammonia to be about 9.7. The dissolved oxygen concentration is less than 1 μg/kg, and the ammonia concentration is 50 to 100 μg/L. A slow strain rate test (SSRT) was employed to evaluate the SCC sensitivity in SCW with various types and concentrations of impurity ions. After the SSRT test, the fracture surfaces of the specimen were observed and analyzed using scanning electron microscope (SEM). In SCW environments containing 3 g/L Cl − or 5 g/L SO 4 2− , local intergranular cracks were found at the fracture surface edges of the specimens, indicating a certain sensitivity to SCC. When the concentration of SO 4 2− was reduced to 5 mg/L, the intergranular crack characteristics of the Alloy 690TT became less apparent, suggesting a high resistance to SCC under low SO4 2− concentrations.

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Publication Details

Journal
Journal of Physics Conference Series
Published
2024-08-01
DOI
https://doi.org/10.1088/1742-6596/2821/1/012013
Primary Topic
Nuclear Engineering Thermal-Hydraulics
Type
article
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article

Impact of Impurity Ions in Secondary Circuit Water on Cracking Behaviour of PWR Steam Generator 690TT Tube

Xinhe Xu, Hang Qiao, Zhaohui Tian, Tongming Cui et al.
Journal of Physics Conference Series
Nuclear Engineering Thermal-Hydraulics
article

Impact of Impurity Ions in Secondary Circuit Water on Cracking Behaviour of PWR Steam Generator 690TT Tube

Xinhe Xu, Hang Qiao, Zhaohui Tian, Tongming Cui, Lijun Song, Zhanpeng Lu
article en

Abstract

Abstract The impact of impurity ions on stress corrosion cracking (SCC) sensitivity of steam generator heat-exchange tube material Alloy 690TT in secondary circuit water (SCW) was studied at 285 °C. The pH of the test solution was adjusted using ammonia to be about 9.7. The dissolved oxygen concentration is less than 1 μg/kg, and the ammonia concentration is 50 to 100 μg/L. A slow strain rate test (SSRT) was employed to evaluate the SCC sensitivity in SCW with various types and concentrations of impurity ions. After the SSRT test, the fracture surfaces of the specimen were observed and analyzed using scanning electron microscope (SEM). In SCW environments containing 3 g/L Cl − or 5 g/L SO 4 2− , local intergranular cracks were found at the fracture surface edges of the specimens, indicating a certain sensitivity to SCC. When the concentration of SO 4 2− was reduced to 5 mg/L, the intergranular crack characteristics of the Alloy 690TT became less apparent, suggesting a high resistance to SCC under low SO4 2− concentrations.

Journal of Physics Conference SeriesVol. 2821(1)
Quality and Reliability (Greece) (GR), Suzhou Research Institute (CN), Shanghai Research Institute of Materials (CN)
Clean water and sanitation
Openalex Percentile: Top 80%
Nuclear Engineering Thermal-Hydraulics
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