Elsevier 《Progress in Nuclear Energy》共同主编
《ASME Journal of Nuclear Engineering and Radiation Science》副主编
Elsevier 《Nuclear Science and Technology》编委
《Journal of Energy》编委
国际学术会议ICONE（International Conference On Nuclear Engineering）技术委员会委员、副主席及主席等
教育部全国高校核工程类专业教学指导委员会副主任
中国核工业教育协会副理事长
►研究领域或方向
汽液两相流动与沸腾传热及核反应堆热工水力分析；包括核动力系统稳态与瞬态热工水力特性的理论与实验研究等。
核电厂严重事故现象学。
►科研项目
承担了包括国家自然科学基金、重大专项、国家攻关项目、863项目、国防预研项目及横向科研项目等100余项。
| Paper Name | Author | Publication/Completion Time | Magazine Name |
|---|---|---|---|
| The code development and thermo-hydrodynamic analysis of the reflood during severe accident in PWR | S.P. Niu, Y.P. Zhang, W.X. Tian, S.Z. Qiu, G.H. Su | 2017-01-31 | Annals of Nuclear Energy |
| Analysis of KROTOS KS-2 and KS-4 steam explosion experiments with TEXAS-VI | Chen, RH; Wang, J; Su, GH; Qiu, SZ ; Corradini, ML | 2016-12-30 | NUCLEAR ENGINEERING AND DESIGN |
| Numerical Research for Passive Residual Heat Removal Heat Exchanger under Natural Convection Condition | Ge, Jian1; Cong, Tenglong1; Zhang, Wenwen1; Tian, Wenxi1; Qiu, Suizheng1; Su, Gu | 2016-12-30 | Nuclear Power Engineering |
| Experimental investigation on nanofluid flow boiling heat transfer in a vertical tube under different pressure conditions | Y. Wang, G.H. Su | 2016-10-28 | Experimental Thermal and Fluid Science |
| ECC condensation research in T-junction | Ren WY; Fu XL ;Tian WX,Dong B,Bian JW,Yu GJ,Yang YH | 2016-09-30 | Progress in Nuclear Energy |
| Study effects of the kinetics of local composition diffusion on the melt pool coolability by developing a DBL-LIVE model | Y.P. Zhang, W.X. Tian, S.Z. Qiu, G.H.Su | 2016-07-29 | Progress in Nuclear Energy |
| The COPRA experiments on the in-vessel melt pool behavior in the RPV lower head | Y.P. Zhang, L.T. Zhang, Y.K. Zhou, W.X. Tian, S.Z. Qiu, G.H. Su, B. Zhao, Y.D. Y | 2016-03-31 | Annals of Nuclear Energy |
| The influence of ocean conditions on thermal-hydraulic characteristics of a passive residual heat removal system | Xi, MM ; Wu, YW; Tian, WX; Su, GH ; Qiu, SZ | 2015-11-30 | PROGRESS IN NUCLEAR ENERGY |
| Analysis of Westinghouse MB2 test using the Steam-generator Thermohydraulics Analysis code STAF | Cong, TL ; Zhang, R; Tian, WX ; Su, GH ; Qiu, SZ | 2015-11-30 | ANNALS OF NUCLEAR ENERGY |
| Investigation of severe accident scenario of PWR response to LOCA along with SBO | Hu, L; Zhang, YP ; Li, LZ; Su, GH ; Tian, WX ; Qiu, SZ | 2015-08-31 | PROGRESS IN NUCLEAR ENERGY |
| Investigation of severe accident scenario of PWR response to LOCA along with SBO | Hu, L; Zhang, YP ; Li, LZ; Su, GH ; Tian, WX ; Qiu, SZ | 2015-08-31 | PROGRESS IN NUCLEAR ENERGY |
| Preliminary safety analysis of the PWR with accident-tolerant fuels during severe accident conditions | Wu, XL; Li, W ; Wang, Y; Zhang, YP; Tian, WX; Su, GH; Qiu, SZ ; Liu, T ; Deng, | 2015-06-30 | ANNALS OF NUCLEAR ENERGY |
| Experimental research on the thermal hydraulic characteristics of sodium boiling in an annulus | Qiu, ZC; Ma, ZY ; Qiu, SZ; Su, GH ; Zhang, DL; Wu, YW ; Tian, WX | 2015-01-31 | EXPERIMENTAL THERMAL AND FLUID SCIENCE |
| MAAP5 simulation of the PWR severe accident induced by pressurizer safety valve stuck-open accident | Li,Longze; Zhang,Yapei; Tian,Wenxi; Su,Guanghui; Qiu,Suizheng | 2014-11-30 | PROGRESS IN NUCLEAR ENERGY |
| Preliminary study of coupling CFD code FLUENT and system code RELAP5 | Li,Wei; Wu,Xiaoli; Zhang,Dalin; Su, Guanghui; Tian,Wenxi; Qiu,Suizheng | 2014-11-30 | ANNALS OF NUCLEAR ENERGY |
| Comparison of CORA & MELCOR core degradation simulation and the MELCOR oxidation model | Wang,Jun; Corradini,Michael L.; Fu,Wen; Haskin,Troy; Tian,Wenxi; Zhang,Yapei | 2014-09-30 | NUCLEAR ENGINEERING AND DESIGN |
| Numerical study on the heat transfer characteristics of LIVE-L4 melt pool with a partial solidification process | Zhang,Y.P.; Su,G.H.; Qiu,S.Z.; Tian,W.X.; Gaus-Liu,X.; Kretzschmar,F.; Miasso | 2014-06-30 | PROGRESS IN NUCLEAR ENERGY |
| Thermal-hydraulic performance analysis of IPWR during full pressure start-up mode | L. Zhao, G.H. Su, S.Z. Qiu, Z.L. Wang | 2013-10-31 | Annals of Nuclear Energy |
| Analyses of liquid entrainment through ADS-4 in AP1000 during a typical small break LOCA transient | W.W. Wang, G.H. Su, Z.M. Meng, W.X. Tian, S.Z. Qiu | 2013-10-31 | Annals of Nuclear Energy |
| Research on thermal hydraulic behavior of small-break LOCAs in AP1000 | W.W. Wang, G.H. Su, W.X. Tian, S.Z. Qiu | 2013-10-30 | Nuclear Engineering and Design |
| Republication | Author | Republication date | Publisher |
|---|---|---|---|
| 核电厂通用机械设备 | 苏光辉、武俊梅 | 2016-11-30 | 中国电力出版社 |
| 先进核电厂结构与动力设备 | 秋穗正 苏光辉 田文喜 张大林 巫英伟 张亚培 陈荣华 | 2016-03-31 | 中国原子能出版社 |
| 轻水堆严重事故机理与现象学 | 苏光辉，田文喜，张亚培，秋穗正，陈义学，季松涛，余红星 | 2015-12-31 | 国防工业出版社 |
| 流体动力学 | 倪明久，苏光辉等 | 2014-08-29 | 科学出版社 |
| 《核动力系统热工水力计算方法》 | 苏光辉 秋穗正 田文喜等 | 2013-11-30 | 清华大学 |
| 核反应堆热工水力计算方法 | 苏光辉 郭玉君 秋穗正 张金玲 | 2006-02-06 | 西安交通大学 |
版权所有：西安交通大学 陕ICP备05001571号
技术支持联系电话：
服务邮箱：
欢迎您访问我们的网站，您是第2367529611位访客
