丛腾龙部门：核科学与技术学院

学科：核科学与技术

职务：

职称：副教授

指导
资格：
电话：**

传真：

邮箱：tlcong@hrbeu.edu.cn

邮编：150001

地址：哈尔滨南岗区南通大街145号31号楼443室


个人简介
公告：招收硕士、博士研究生，有意者请联系tlcong@hrbeu.edu.cn
研究领域：
反应堆热工水力与安全
多相计算流体力学


教育经历
2010.9-2016.3，西安交通大学，核科学与技术，工学博士
2006.9-2010.7，西安交通大学，核工程与核技术，本科


工作经历
2018.6-至今，哈尔滨工程大学，副教授
2016.3-2018.5，哈尔滨工程大学，讲师
2014.9-2015.9，美国维斯康星大学麦迪逊，联合培养博士研究生

研究方向
1）沸腾传热的机理实验及理论模型研究
2）严重事故机理实验研究及模型开发
3）反应堆多尺度热工水力特性研究
4）反应堆关键设备的流固热耦合特性研究
5）分子动力学、玻尔兹曼方法在两相流问题中的应用研究
承担项目
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
4 国家自然科学基金青年科学基金项目 《自然循环流动闪蒸的形成机理及不稳定性研究》，23.0万元，2018-2020，参与人
学术交流
招生信息
本课题组招收硕士、博士研究生，有意者请邮件或电话联系。

本科生授课课程
《军用核能技术及其发展》

研究生授课课程
《Thermal Hydraulics in Nuclear Power Technology》

实践性教学
本科生科创项目《液钠物性的不确定性对传热与流动特性的影响》

教学研究课题
社会兼职



专利成果


出版著作


发表论文
论文被引超过170次，H-index=8，H10-index=7
期刊论文
[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.
[13] 丛腾龙, 田文喜, 秋穗正等. 压水堆蒸汽发生器一, 二次侧稳态流场耦合分析[J]. 原子能科学技术, 2014, 48 (5): 836-843.
[14] 丛腾龙, 田文喜, 秋穗正等. 耦合一, 二次侧换热的蒸汽发生器二次侧流场分析[J]. 原子能科学技术, 2014, 48 (8): 1398-1405.
[15] 丛腾龙, 田文喜, 秋穗正等. 蒸汽发生器二次侧三维两相流场稳态计算[J]. 核动力工程, 2014, 35: 37-40.
[16] 韦宏洋, 丛腾龙, 田文喜等. 钠冷行波堆 TP-1 瞬态安全分析[J]. 原子能科学技术, 2013, 47 (11): 2020-2025.
[17] 韦宏洋, 田文喜, 丛腾龙等. 行波堆TP-1堆芯热工水力单通道与子通道分析方法研究[J]. 原子能科学技术, 2013, 47: 2261-2266.
[18] 章静, 丛腾龙, 苏光辉等. 遗传神经网络对水平通道流动沸腾传热系数的预测[J]. 原子能科学技术, 2015, 49 (1): 70-76.
[19] 王成龙, 丛腾龙, 田文喜等. 蒸汽发生器传热管束过冷沸腾区两相流动数值模拟[J]. 原子能科学技术, 2014, 48 (8): 1392-1397.
[20] 王成龙, 丛腾龙, 王泽勇等. 蒸汽发生器传热管一, 二次侧耦合换热及管外过冷沸腾数值研究[J]. 原子能科学技术, 2014, 48 (4): 610-616.
[21] 戈剑, 丛腾龙, 张文文等. 自然对流条件下 PRHEHX 传热特性数值研究[J]. 核动力工程, 2016, 37 (1): 129-132.
[22] 张蕊, 田文喜, 丛腾龙等. 湍流模型对过冷沸腾计算影响分析[J]. 原子能科学技术, 2015, 49 (8): 1366-1373.
[23] 张文文, 丛腾龙, 田文喜等. 非能动余热排出换热器换热能力数值分析[J]. 原子能科学技术, 2015, 49 (6): 1032-1038.
[24] 黄思洋, 张大林, 丛腾龙等. 基于 FLUENT 软件耦合点堆中子动力学模型的行波堆热工水力分析[J]. 中国科技论文, 2015, 10 (11): 1253-1257.

会议论文
[25] Tenglong Cong, Rui Zhang, Wenxi Tian, et al. Development, validation and application of a steam generator thermohycraulics analysis code STAF[C]. ANS Annual Meeting, Jun 7-11, 2015, San Antonio, TX, USA: ANS, 2015.
[26] Tenglong Cong, Rui Zhang, Wenxi Tian, et al. Comparison of two ways to predict shear-drive liquid film[C]. NURETH-16, Aug, 30 - Sep 4, 2015, Chicago, IL, USA: ANS, 2015.
[27] Tenglong Cong, Rui Zhang, Wenxi Tian, et al. Development and validation of STAF: a Steam generator 3D Thermohydrulics Analysis code based on Fluent[C]. ICONE23, May 17-21, 2015, Chiba, Japan: ASME, 2015.
[28] Tenglong Cong, Hongyang Wei, Wenxi Tian, et al. Transient and safety analysis code for TP-1 sodium cooled TWR[C]. ICONE21, Jul 29-Aug 2, Chengdu, China: ASME, 2013.
[29] Tenglong Cong, Laishun Wang, Wenxi Tian, et al. Three dimensional numerical analysis of thermal-hydraulic behaviors of UTSG based on Fluent code[C]. International Seminar on Subchannel Analysis CFD modeling and verification, CHF experiment and benchmarking, Aug. 3-4, Xi'an, China, 2013.
[30] Tenglong Cong, Wenxi Tian, Guanghui Su, et al. Development and Application of a UTSG Thermal-hydraulic Analysis Code[C]. ICONE22, Jul 7-11, Prague, Czech Republic: ASME, 2014.
[31] Tenglong Cong, Wenxi Tian, Guanghui Su, et al. Analysis on thermal-hydraulics of UTSG by STAF code[C]. Embedded Topical Meeting on Advances in Thermal Hydraulics (ATH 14), Jun 15-19, 2014, Reno, NV, USA: ANS, 2014.
[32] Tenglong Cong, Wenxi Tian, Guanghui Su, et al. Development and application of a UTSG thermal-hydraulic analysis code[C]. ICAPP2014, Apr 6-9, Charlotte, US: ANS, 2014.
[33] Tenglong Cong, Wenxi Tian, Guanghui Su, et al. Three-dimensional steady simulation on two-phase flow in secondary side of steam generator[C]. ICONE21, Jul 29-Aug 2, Chengdu, China: ASME, 2013.
[34] Tenglong Cong, Rong Cai, Zhaoming Meng, et al. Study on the secondary side of steam generator based on porous media model[C]. WORTH-6, Apr 11-13, Busan, Korea, 2013.
[35] Wenxi Tian, Tenglong Cong, Suizheng Qiu, et al. Application of CFD in nuclear thermohydraulics[C]. 7th Joint Internatinal Symposium on Nuclear Science and Technology XJTU-UT-SJTU Joint Workshop, Oct 12-15, 2014, Xi'an, China, 2014.
[36] Wenxi Tian, Tenglong Cong. Investigation on Flow Characteristics in the Secondary Side of AP1000 Steam Generator[C]. 6th Joint International Symposium on Nuclear Science and Technology SJTU-UT-XJTU Joint Workshop, Aug. 11-14, Shanghai, China, 2013.
荣誉

奖励



English

Contact:
Email: tlcong@hrbeu.edu.cn
Tel: +**299
Add: Room 443, Building 31, 145 Nantong St., Harbin, Heilongjiang, P.R. China.

Education:
PhD, 2016, Xi'an Jiaotong University, Nuclear Engineering
BS, 2010, Xi'an Jiaotong University, Nuclear Engineering


Occupation:
Associate Professor, 2018, Harbin Engineering University, College of Nuclear Science and Technology
Assistance Professor, 2016, Harbin Engineering University, College of Nuclear Science and Technology
Visiting scholar, 2014-2015, University of Wisconsin-Madison, Engineering Physics

Research:
Nuclear thermohydraulics;
Boiling heat transfer and two-phase flow;
Computational fluid dynamics;
Fluid structure interaction;
Lattice boltzmann method.



自定义模块2



自定义模块3