丛腾龙 - 上海交通大学 - 机械与动力工程学院

个人简介

教育背景 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，学士工作经历 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，讲师科研项目 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，负责人教学工作本科生课程：热力系统设计与实践、反应堆热工水力学研究生课程：数值反应堆多物理分析荣誉奖励 2019.1 陕西省优秀博士学位论文

研究领域

核燃料元件设计多物理场耦合分析计算多相流体力学反应堆热工水力

近期论文

查看导师新发文章（温馨提示：请注意重名现象，建议点开原文通过作者单位确认）

[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.