Research Fields

1. Foundamental research on flow and heat transfer in new type of fuel element channels
    新型核动力换热元件热工水力基础特性理论与实验研究

2. Development of code on thermal-hydraulic and safety ananlysis of nuclear reactor
    反应堆热工水力与安全分析程序开发研究

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

4. Application of advanced numerical method in nuclear thermalhydraulics field
    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

5. Coupling analysis of neutronics and thermalhydraulics
    中子物理-热工水力耦合研究

6. Design, safety evalution and optimization of advanced reactors(AP,SCWR,MSR,SFR etc..)     
   先进堆堆芯设计、安全评价及优化研究

Science Project

No entries were found.
Project number Project name Project origin Start time Roles Project kind
U1967203 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 2020-01~2024-12 负责人 Vertical project
SQ2017YFE030069 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 2018-8~ 负责人 Vertical project
20130970 非能动余热排出热交换器自然对流条件下的传热分析研究 其他 2013-9~ 负责人 Vertical project
JK-2013-0006 核电严重事故分析软件 国家攻关项目 2013-7~ 负责人 Vertical project
20130329 多孔介质模型在堆芯三维热工水力设计中的应用研究 其他 2013-1~ 负责人 horizontal project
20121069 铅铋反应堆子通道分析程序开发 其他 2012-1~ 负责人 horizontal project
51100849 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 2011-9~ 负责人 Vertical project
2011ZX06004-024-02-02-02 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 2011-1~ 负责人 Vertical project
91126009 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 2011-12~ 负责人 Vertical project
2009GB109000HZ2 基于RELAP5的液态TBM专用安全分析软件开发 973项目 2010-1~ 负责人 Vertical project
20090201120002 基于MPS方法的液态重金属内汽泡动力学模拟及两相流压降预测研究 国家教育部项目 2010-1~ 负责人 Vertical project
20101210 超临界水冷堆系统流动不稳定性研究 国家攻关项目 2010-10~ 负责人 horizontal project
教育部留学回国人员启动基金 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 2010-10~ 负责人 Vertical project
10905045 基于MPS方法的液态铅铋内气泡上升流模拟及气泡泵提升自然循环机理研究 国家自然科学基金项目 2009-1~ 负责人 Vertical project

Awards

No entries were found.
Awards Name Year Awards Type Awards Level Offer
先进核能系统两相流动密度波不稳定性的理论研究 2008 局厅级科技成果奖 一等奖 陕西省教育厅
核动力系统热工水力分析理论模型的研究 2007 省部级科技成果奖 二等奖 陕西省

Paper

No entries were found.
Paper Name Author Publication/Completion Time Magazine Name
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