Ph.D., 2016, Xi'an Jiaotong University, Nuclear Engineering
B.E., 2010, Xi'an Jiaotong University, Nuclear Engineering
Joint PhD student, 2014.9-2015.9, University of Wisconsin-Madison, Engineering Physics

Associate Professor, 2020, Shanghai Jiaotong University, School of Nuclear Science and Engineering
Associate Professor, 2018, Harbin Engineering University, College of Nuclear Science and Technology
Assistance Professor, 2016, Harbin Engineering University, College of Nuclear Science and Technology

Thermohydraulics
Computational Fluid Dynamics

[1] Cong T, Zhang R, Tian W, et al. Analysis of Westinghouse MB2 test using the Steam-generator Thermohydraulics Analysis code STAF[J]. Annals of Nuclear Energy, 2015, 85: 127-136.
[2] Cong T, Zhang R, Tian W, et al. Development and preliminary validation of a steam generator 3D thermohydraulics analysis code STAF[J]. Nuclear engineering and design, 2016, 298: 135-148.
[3] Cong T, Zhang R, Tian W, et al. Effects of power level on thermal-hydraulic characteristics of steam generator[J]. Progress in Nuclear Energy, 2015, 81: 245-253.
[4] Cong T, Tian W, Su G, et al. Three-dimensional study on steady thermohydraulics characteristics in secondary side of steam generator[J]. Progress in Nuclear Energy, 2014, 70: 188-198.
[5] Cong T, Su G, Qiu S, et al. Applications of ANNs in flow and heat transfer problems in nuclear engineering: a review work[J]. Progress in Nuclear Energy, 2013, 62: 54-71.
[6] Cong T, Peng M, Zhang Z. Preliminary applications of CFD methodology on analysis of the single-phase laminar natural circulation under swing conditions[J]. Progress in Nuclear Energy, 2017, 97: 1-10.
[7] Cong T, Chen R, Su G, et al. Analysis of CHF in saturated forced convective boiling on a heated surface with impinging jets using artificial neural network and genetic algorithm[J]. Nuclear engineering and design, 2011, 241 (9): 3945-3951.
[8] Wang C, Cong T, Qiu S, et al. Numerical prediction of subcooled wall boiling in the secondary side of SG tubes coupled with primary coolant[J]. Annals of Nuclear Energy, 2014, 63: 633-645.
[9] Zhang R, Cong T, Tian W, et al. CFD analysis on subcooled boiling phenomena in PWR coolant channel[J]. Progress in Nuclear Energy, 2015, 81: 254-263.
[10] Zhang R, Cong T, Tian W, et al. Effects of turbulence models on forced convection subcooled boiling in vertical pipe[J]. Annals of Nuclear Energy, 2015, 80: 293-302.
[11] Zhang R, Cong T, Tian W, et al. Prediction of CHF in vertical heated tubes based on CFD methodology[J]. Progress in Nuclear Energy, 2015, 78: 196-200.
[12] Tian M, Cong T, Ma Z, et al. A new unidentified leak detection method based on the EVR ventilation condensate[J]. Progress in Nuclear Energy, 2017, 98: 11-22.