T. Jin

Weibull stress analysis for the corner crack in reactor pressure vessel nozzle

Yuebing Li, Mingjue Zhou, Dasheng Wang, 2019 .

Measurement of internal residual stress field in multi-layer fillet welded joint of ultra-thick circular plate and tube

Y. Lei, Jian Lin, T. Jin, 2019, The International Journal of Advanced Manufacturing Technology.

Quick Evaluation Method for Defect Exceeding the Allowable Flaw Size in Pressure Vessel of Nuclear Reactor for Power Plant and Space Heating

Yuebing Li, Dasheng Wang, T. Jin, 2021, Frontiers in Energy Research.

Numerical and experimental sensitivity analysis on the welding pool shape in TIG welding

P. Liu, T. Jin, X. Kong, 2017, 2017 IEEE 7th International Conference on Power and Energy Systems (ICPES).

The Investigation of the Fracture Behavior of a Chinese 9% Cr Steel Welded Joint under Creep-Fatigue Interactive Loading

Pan Liu, Yuebing Li, T. Jin, 2021, Applied Sciences.

Study on structural integrity of reactor pressure vessel with various ablation under core meltdown accident

J. Mao, Dasheng Wang, T. Jin, 2022, Nuclear Engineering and Design.