(1.)Basic Information


        Tian Wenxi,  Lecturer
       Xi’an Jiaotong University
   Email: wxtian@mail.xjtu.edu.cn

(7.)Contact

Tian Wenxi
Department of Nuclear Science and Technology, 
School of Energy and Power Engineering, 
Xi’an Jiaotong University, 710049.
No.28 Xianning west road, Xi’an, Shaanxi,China.
Email: wxtian@mail.xjtu.edu.cn

(6.)Teaching

Lectures for undergraduate:

1."Nuclear Rector thermalhydraulics"

2."Nuclear Power Plant System and Structure "

3.“Nuclear Power Steam Turbine”

(3.)Education

Sep.1997－Jul.2001,  Undergraduate course in Xi’an Jiaotong University 
Sep.2001－May.2006, Doctor course in Xi’an Jiaotong University
Jul.2006－Jan,2010,  Lectuer in Xi’an Jiaotong University
Oct.2007－Apr. 2009,  Visiting researcher in the University of Tokyo, Japan

Apr. 2009-Jan.2010,  Lectuer in Xi’an Jiaotong University
Feb.2010－Nov.2014., Associate prof. in Xi’an Jiaotong University

Dec.2014－present,  Prof. in Xi’an Jiaotong University

(5.)Scientific Research fields

1. Foundamental research on flow and heat transfer in new type of fuel element channels 

2. Development of code on thermal-hydraulic and safety analysis of nuclear reactor

3. Multidimensional-coupling numetical analysis using system code, subchannel code and CFD softwares.

4. Application of advanced numerical method in nuclear thermalhydraulics field

5. Coupling analysis of neutronics and thermalhydraulics

6. Design, safety evalution and optimization of advanced reactors(AP,SCWR,MSR,SFR etc..) 

Publications

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论文标题 作者 发表/完成日期 期刊名称
Comparative study of transient thermal–hydraulic characteristics of SCWRs with different core design Dahuan Zhu, Wenxi Tian, Suizheng Qiu, Guanghui Su 2012-11-01 Annals of Nuclear Energy
Development of TSAC1.0 and application to reactivity insertion accident of CARR Ronghua Chen, G.H. Su, Wenxi Tian et al 2011-01-01 Progress in Nuclear Energy
Numerical investigation on bubble dynamics during flow boiling using moving particle semi-implicit method Ronghua Chen, Wenxi Tian, G.H. Su, Suizheng Qiu 2010-10-06 Nuclear Engineering and Design
Numerical study on flow andheat transfer characteristics in therod bundle channels under super critical pressure condition Xingbo Yang, Guanghui Su, Wenxi Tian et al. 2010-10-01 Annals of Nuclear Energy
Numerical computation of thermally controlled steam bubble condensation using Moving Particle Semi-implicit (MPS) method Tian Wenxi, Yuki Ishiwatari, Yoshiaki Oka 2010-01-10 Annals of Nuclear Energy
Numerical simulation on void bubble dynamics using moving particle semi-implicit method Wenxi Tian Yuki Ishiwatari Yoshiaki Oka 2009-11-01 Nuclear Engineering and Design
Numerical simulation and optimization on valve-induced water hammer characteristics for parallel pump feedwater system Wenxi Tian, G.H. Su, Gaopeng Wang, Suizheng Qiu 2008-12-10 Annals of Nuclear Energy
Analysis on natural circulation capacity of the CARR Tian Wenxi, Qiu Suizheng, Su Guanghui Jia Dounan 2007-06-10 Nuclear Science & Techniques
Thermohydraulic and safety analysis on China advanced research reactor under station blackout accident Tian W X, Qiu S Z, Su G H, Jia D N 2007-03-10 Annals of Nuclear Energy
Investigations on post-dryout heat transfer in bilaterally heated annular channels Tian W X, Qiu S Z, Jia D N. 2006-02-10 Annals of Nuclear Energy
Development of a Thermal-hydraulic Analysis Code for CARR Tian W X, Qiu S Z, Su G H, Jia D N 2005-02-10 Annals of Nuclear Energy
Study on dryout point in vertical narrow annuli Tian Wenxi, Myint Aye, Jia Dounan 2005-02-10 Nuclear Science & Techniques
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