Stress corrosion cracking behavior and mechanism of scratched Alloy 690TT in lead-containing caustic solution.Corrosion Science,2025,245,112702.

Effect of temperature on corrosion fatigue behavior of Inconel Alloy 690TT steam generator tube.Corrosion Science,2024,227,111741.

Corrosion fatigue damage mechanism and life evaluation of Inconel Alloy 690TT steam generator tube in high temperature pressurized water.Corrosion Science,2023,212,110953.

Effects of dissolved hydrogen on corrosion fatigue crack growth behavior of 316LN stainless steel in high temperature pressurized water environment.Corrosion Science,2024,232,112041.

Size effect of scratches on the degradation behavior of Alloy 690TT in high temperature caustic solution.Corrosion Science,2021,182,10931.

Oxide properties of deformed Alloy 690TT in caustic solution at high temperature.Corrosion Science,2020,174,108806.

Study on the SCC behavior induced by creep cavities on scratched surface of Alloy 690TT in high temperature water.Corrosion Science,2022,196,110017.

Fatigue life prediction of nuclear reactor main bolt based on temperature effect and size effect.International Journal of Fatigue,2021,152,106443.

High cycle fatigue behavior and numerical evaluation of Alloy 690TT steam generator tube.International Journal of Fatigue,2020,137,105662.

Fatigue crack initiation and propagation behavior of Inconel Alloy 690TT steam generator tube.Materials Science and Engineering A,2021,811,141090.