教育及工作经历

（一）2014.12- 至今 西安交大核能系 教授

（二）2010.3- 2014.11 西安交大核能系 副教授

（三）2007.10-2009.4 日本东京大学 博士后

（四）2006.8-2010.2 西安交大核能系 讲师

（五）2001.9-2006.5 西安交大核能系 硕博连读

（六）1997.9-2001.7 西安交大核能系 本科

研究领域（方向）

（一）新型核动力换热元件热工水力基础特性理论与实验研究

（二）反应堆热工水力与安全分析程序开发研究

（三）多尺度耦合(系统程序/子通道程序/三维CFD程序)的反应堆热工水力数值模拟研究

（四）先进数值方法(MPS，MOC，VOF)在核反应堆热工水力领域的应用研究

（五）中子物理-热工水力耦合研究

（六）先进堆堆芯设计、安全评价及优化研究

科研项目

（一）核热推进反应堆复杂系统热工过程多物理场耦合关键技术研究，国家自然科学基金项目，负责人

（二）基于多物理场耦合的CFETR 包层三维时空能量沉积及热工安全特性研究，国家攻关项目，负责人

（三）冷却剂沸腾机理，中国原子能科学技术研究院，负责人

（四）XXX条件下冷却剂沸腾临界行为特性研究，国防973课题，负责人

（五）核电严重事故分析软件，国家攻关项目，负责人

（六）严重事故堆芯再淹没和碎片床形成及冷却研究，国家攻关项目，负责人

（七）COSINE堆芯物理—热工设计及系统安全分析软件包研发，重大专项，负责人

（八）基于行波堆技术的核燃料增殖与嬗变关键基础理论研究，国家自然科学基金项目，负责人

（九）超临界水冷堆系统流动不稳定性研究，国家攻关项目，负责人

（十）基于移动例子半隐式(MPS)方法的汽泡冷凝动力学研究，国家教育部项目，负责人   

学术及科研成果、专利、论文

[1]Wenxi Tian, Yuki Ishiwatari, Satoshi Ikejiri, et al. Numerical Simulation on Direct Contact Condensation of Single Bubble in Subcooled Water using MPS method[J]. AIP Conference Proceedings, 2010, 1207(1):933.

[2]Dahuan Zhu,Wenxi Tian,Hao Zhao,Yali Su,Suizheng Qiu,Guanghui Su. Comparative study of transient thermal–hydraulic characteristics of SCWRs with different core design[J]. Annals of Nuclear Energy,2013,51.

Kailun Guo, Chenglong Wang, Dalin Zhang, et al. INVESTIGATIONS OF NEAR-WALL BUBBLE BEHAVIOR IN WIRE HEATERS POOL BOILING[J]. Thermal Science, 2021, 25(5):3957 - 3967.

Wenxi Tian,  Qiang Lian,  Suizheng Qiu, et al. Research of two‐phase density wave instability in reactor core channels with rolling motion[J]. International Journal of Energy Research, 2020, 44(9):7323-7341.

Yu Liang,  Dalin Zhang,  Yutong Chen, et al. An experiment study of pressure drop and flow distribution in subchannels of a 37-pin wire-wrapped rod bundle[J]. Applied Thermal Engineering, 2020, 174

Chenglong Wang,  Hao Qin,  Wenxi Tian, et al. Transient analysis of tritium transport characteristics of thorium molten salt reactor with solid fuel[J]. Annals of Nuclear Energy, 2020, 141:107337-107337.

Di Liu,  Wenxi Tian,  Mengmeng Xi, et al. Study on safety boundary of flow instability and CHF for parallel channels in motion[J]. Nuclear Engineering and Design, 2018, 335:219-230.

Jian Ge,  Wenxi Tian,  Suizheng Qiu, et al. CFD simulation of secondary side fluid flow and heat transfer of the passive residual heat removal heat exchanger[J]. Nuclear Engineering and Design, 2018, 337:27-37.

Juanli Zuo,  Wenxi Tian,  Ronghua Chen, et al. Research on enhancement of natural circulation capability in lead–bismuth alloy cooled reactor by using gas-lift pump[J]. Nuclear Engineering and Design, 2013, 263:1-9.

Juanli Zuo,  Wenxi Tian,  Ronghua Chen, et al. Two-dimensional numerical simulation of single bubble rising behavior in liquid metal using moving particle semi-implicit method[J]. Progress in Nuclear Energy, 2013, 64:31-40.

Wenxi  Tian, Yuki  Ishiwatari, Satoshi  Ikejiri, et al. Numerical Simulation on Direct Contact Condensation of Single Bubble in Subcooled Water using MPS method[J]. AIP Conference Proceedings, 2010, 1207(1):933.

Kailun Guo, Chenglong Wang, Dalin Zhang, et al. INVESTIGATIONS OF NEAR-WALL BUBBLE BEHAVIOR IN WIRE HEATERS POOL BOILING[J]. Thermal Science, 2021, 25(5):3957 - 3967.

Wenxi Tian,  Qiang Lian,  Suizheng Qiu, et al. Research of two‐phase density wave instability in reactor core channels with rolling motion[J]. International Journal of Energy Research, 2020, 44(9):7323-7341.

Yu Liang,  Dalin Zhang,  Yutong Chen, et al. An experiment study of pressure drop and flow distribution in subchannels of a 37-pin wire-wrapped rod bundle[J]. Applied Thermal Engineering, 2020, 174

Chenglong Wang,  Hao Qin,  Wenxi Tian, et al. Transient analysis of tritium transport characteristics of thorium molten salt reactor with solid fuel[J]. Annals of Nuclear Energy, 2020, 141:107337-107337.

Di Liu,  Wenxi Tian,  Mengmeng Xi, et al. Study on safety boundary of flow instability and CHF for parallel channels in motion[J]. Nuclear Engineering and Design, 2018, 335:219-230.

Jian Ge,  Wenxi Tian,  Suizheng Qiu, et al. CFD simulation of secondary side fluid flow and heat transfer of the passive residual heat removal heat exchanger[J]. Nuclear Engineering and Design, 2018, 337:27-37.

Juanli Zuo,  Wenxi Tian,  Ronghua Chen, et al. Research on enhancement of natural circulation capability in lead–bismuth alloy cooled reactor by using gas-lift pump[J]. Nuclear Engineering and Design, 2013, 263:1-9.

Juanli Zuo,  Wenxi Tian,  Ronghua Chen, et al. Two-dimensional numerical simulation of single bubble rising behavior in liquid metal using moving particle semi-implicit method[J]. Progress in Nuclear Energy, 2013, 64:31-40.

Wenxi  Tian, Yuki  Ishiwatari, Satoshi  Ikejiri, et al. Numerical Simulation on Direct Contact Condensation of Single Bubble in Subcooled Water using MPS method[J]. AIP Conference Proceedings, 2010, 1207(1):933.

[3] Juanli Zuo, Wenxi Tian, Ronghua Chen, et al. Two-dimensional numerical simulation of single bubble rising behavior in liquid metal using moving particle semi-implicit method[J]. Progress in Nuclear Energy, 2013, 64:31-40.

[4]Juanli Zuo, Wenxi Tian, Ronghua Chen, et al. Research on enhancement of natural circulation capability in lead–bismuth alloy cooled reactor by using gas-lift pump[J]. Nuclear Engineering and Design, 2013, 263:1-9.

[5]Jian Ge, Wenxi Tian, Suizheng Qiu, et al. CFD simulation of secondary side fluid flow and heat transfer of the passive residual heat removal heat exchanger[J]. Nuclear Engineering and Design, 2018, 337:27-37.

[6]Di Liu, Wenxi Tian, Mengmeng Xi, et al. Study on safety boundary of flow instability and CHF for parallel channels in motion[J]. Nuclear Engineering and Design, 2018, 335:219-230.

[7]Chenglong Wang, Hao Qin, Wenxi Tian, et al. Transient analysis of tritium transport characteristics of thorium molten salt reactor with solid fuel[J]. Annals of Nuclear Energy, 2020, 141:107337-107337.

[8]Yu Liang, Dalin Zhang, Yutong Chen, et al. An experiment study of pressure drop and flow distribution in subchannels of a 37-pin wire-wrapped rod bundle[J]. Applied Thermal Engineering, 2020, 174

[9]Wenxi Tian, Qiang Lian, Suizheng Qiu, et al. Research of two‐phase density wave instability in reactor core channels with rolling motion[J]. International Journal of Energy Research, 2020, 44(9):7323-7341.

[10]Kailun Guo, Chenglong Wang, Dalin Zhang, et al. INVESTIGATIONS OF NEAR-WALL BUBBLE BEHAVIOR IN WIRE HEATERS POOL BOILING[J]. Thermal Science, 2021, 25(5):3957 - 3967.