2010.9-2016.3，西安交通大学，核科学与技术，工学博士
2014.9-2015.9，维斯康星大学麦迪逊，工程物理，联培博士
2006.9-2010.7，西安交通大学，核工程与核技术，学士

2020.6-至今，上海交通大学，核科学与工程学院，副教授
2018.6-2020.5，哈尔滨工程大学，核科学与技术学院，副教授
2016.3-2018.5，哈尔滨工程大学，核科学与技术学院，讲师

反应堆热工水力学
计算流体力学

1 国家自然科学基金青年科学基金项目 《含气溶胶和不凝气体的蒸汽冷凝回流传热特性研究》，27.0万元，2018-2020，负责人
2 核能开发科研项目子专题 《XXX流固热耦合XX建模与数值求解技术》，650.0万元，2017-2020，负责人
3 国防科技工业核动力创新中心基金项目 《堆芯异物滞留特性及其对安全的影响研究》，10.0万元，2018，负责人

https://www.scopus.com/authid/detail.uri?authorId=51260938200
[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.

2019.1 陕西省优秀博士学位论文