教育及工作经历

（一）2020.6-至今 西安交通大学 核科学与技术专业 教授

（二）2017.12-2020.5 西安交通大学 核科学与技术专业 副教授

（三）2015.3-2017.11 西安交通大学 核科学与技术专业 讲师

（四）2008.9-2013.3 西安交通大学 核科学与技术专业  博士

（五）2004.9-2008.7 西安交通大学 核工程与核技术专业  学士

研究领域（方向）

（一）核反应堆热工水力与安全

（二）核反应堆严重事故分析

（三）铅基核反应堆

（四）核聚变反应堆

（五）先进粒子法

科研项目

（一）燃料元件裂变产物向液态铅铋合金冷却剂的释放机理研究，国家自然科学基金项目，负责人

（二）铅基反应堆SGTR事故中铅水相互作用机理研究，国家自然科学基金项目，负责人

（三）基于MPS方法的铅基反应堆严重事故下燃料元件失效熔化及燃料迁徙行为研究，国家自然科学基金项目，负责人

（四）核反应堆严重事故工况下蒸汽爆炸研究，2016年陕西省高校科协青年人才托举计划资助项目，负责人

（五）基于MPS方法的UO2-Zr弥散型板状燃料元件化学消熔、高温熔化及熔融物迁徙行为机理研究，国家自然科学基金项目，负责人

（六）基于MPS方法的ADS颗粒流靶熔化事故分析，中国科学院战略性先导科技专项，负责人

（七）燃料棒消熔机理与烛化行为研究，博士后基金，负责人

学术及科研成果、专利、论文

[1]Wenwen Zhang,Chenglong Wang,Ronghua Chen,Wenxi Tian,Suizheng Qiu,G.H. Su. Preliminary design and thermal analysis of a liquid metal heat pipe radiator for TOPAZ-II power system[J]. Annals of Nuclear Energy,2016,97.

[2]Ronghua Chen,Maolin Tian,Sen Chen,Wenxi Tian,G.H. Su,Suizheng Qiu. Three dimensional thermal hydraulic characteristic analysis of reactor core based on porous media method[J]. Annals of Nuclear Energy,2017,104.

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] Ronghua Chen,Yonglin Li,Kailun Guo,Wenxi Tian,Suizheng Qiu,G.H. Su. Numerical investigation on the dissolution kinetics of ZrO2 by molten zircaloy using MPS method[J]. Nuclear Engineering and Design,2017,319.

[4]Ronghua Chen,Chenxi Li,Jun Wang,G.H. Su,Suizheng Qiu,M.L. Corradini. Analysis of the dynamic pressure from ex-vessel steam explosion for pressurized water reactor[J]. Progress in Nuclear Energy,2017,100.

[5]Ronghua Chen,Kailun Guo,Yanshi Zhang,Wenxi Tian,Suizheng Qiu,G.H. Su. Numerical analysis of the granular flow and heat transfer in the ADS granular spallation target[J]. Nuclear Engineering and Design,2018,330.

[6]Chen Ronghua,Zhang Minghao,Guo Kailun,Zhao Dawei,Tian Wenxi,Su Guanghui,Qiu Suizheng. Numerical Study of Bubble Rising and Coalescence Characteristics under Flow Pulsation Based on Particle Method[J]. Science and Technology of Nuclear Installations,2019,2019.

[7]Ronghua Chen,Penghui Zhang,Pan Ma,Bing Tan,Zhangli Wang,Di Zhang,Wenxi Tian,Suizheng Qiu,G.H. Su. Experimental study of the steam condensate dripping behavior on the containment dome[J]. Nuclear Engineering and Design,2019,346.

[8]Ronghua Chen,Chunhui Dong,Kailun Guo,Wenxi Tian,Suizheng Qiu,G.H. Su. Current achievements on bubble dynamics analysis using MPS method[J]. Progress in Nuclear Energy,2020,118.

[9]Ronghua Chen,Qinghang Cai,Penghui Zhang,Yonglin Li,Kailun Guo,Wenxi Tian,Suizheng Qiu,G.H. Su. Three-dimensional numerical simulation of the HECLA-4 transient MCCI experiment by improved MPS method[J]. Nuclear Engineering and Design,2019,347.

[10]Ronghua Chen,Penghui Zhang,Bing Tan,Pan Ma,Zhangli Wang,Di Zhang,Wenxi Tian,Suizheng Qiu,G.H. Su. Steam condensation on a downward-facing plate in presence of air[J]. Annals of Nuclear Energy,2019,132.