叢騰龍，男，上海交通大學核科學與工程學院副教授。
基本介紹
研究領域,教育經歷,工作經歷,榮譽獎勵,代表性論文專著,
研究領域
反應堆熱工水力與安全
計算流體力學。
教育經歷
2014.9-2015.9，維斯康星大學麥迪遜，工程物理，聯培博士
2006.9-2010.7，西安交通大學，核工程與核技術，學士
工作經歷
2020.6-至今，上海交通大學，核科學與工程學院，副教授
2018.6-2020.5，哈爾濱工程大學，核科學與技術學院，副教授
2016.3-2018.5，哈爾濱工程大學，核科學與技術學院，講師
榮譽獎勵
2019.1 陝西省優秀博士學位論文
代表性論文專著
[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.
