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。
| 论文标题 | 作者 | 发表/完成日期 | 期刊名称 |
|---|---|---|---|
| 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 |
| Code development and safety analyses for Pb-Bi-cooled direct contact boiling water fast reactor (PBWFR) | Y.H. Tian, G.H. Su, J. Wang, W.X. Tian, S.Z. Qiu | 2013-09-30 | Progress in Nuclear Energy |
| A simple novel and fast computational model for the LIVE-L4 | Y.P. Zhang, G.H. Su, S.Z. Qiu, W.X. Tian, X. Gaus-Liu, F. Kretzschmar, A. Miasso | 2013-09-30 | Progress in Nuclear Energy |
| Analysis of KROTOS steam explosion experiments using the improved fuel-coolant-lnteraction code TEXAS-VI | R.H. Chen, M.L. Corradini, G.H. Su, S.Z. Qiu | 2013-05-31 | Nuclear Science and Engineering |
| Applications of ANNs in flow and heat transfer problems in nuclear engineering: A review work | Tenglong Cong, Guanghui Su, Suizheng Qiu, Wenxi Tian | 2013-01-31 | Progress in Nuclear Energy |
| Development of a solidification model for TEXAS-VI code and application to FARO L14 analysis | R.H. Chen, G.H. Su, S.Z. Qiu, M.L. Corradini | 2013-01-07 | Nuclear Science and Engineering |
| An improved mechanistic critical heat flux model and its application to motion conditions | W.X. Liu, W.X. Tian, Y.W. Wu, G.H. Su, S.Z. Qiu, X. Yan, Y.P. Huang, D.X. Du | 2012-11-30 | Progress in Nuclear Energy |
| A theoretical CHF model for downward facing surfaces and gaps under saturated boiling | Yu, HX; Zhang, YP; Su, GH; Qiu, SZ; Tian, WX | 2012-10-31 | INTERNATIONAL JOURNAL OF MULTIPHASE FLOW |
| Theoretical study on the characteristics of critical heat flux in vertical narrow rectangular channels | D.X. Du, W.X. Tian, G.H. Su, S.Z. Qiu, Y.P. Huang, X. Yan | 2012-04-27 | Applied Thermal Engineering |
| Development of a thermal-hydraulic safety analysis code RETAC for AP1000 | Wang, WW; Tian, WX ; Su, GH; Qiu, SZ | 2012-03-31 | PROGRESS IN NUCLEAR ENERGY |
| Numerical study on annular tube once-through steam generator using compressible flow model | Z.L. Wang, W.X. Tian, Y.W. Wu, S.Z. Qiu, G.H. Su | 2012-01-31 | Annals of Nuclear Energy |
| Numerical research on oscillation of two-phase flow in multichannels under rolling motion | Youjia Zhang, Guanghui Su, Suizheng Qiu, Wenxi Tian, Hua Li, Libo Qian, Yong Li, | 2011-12-30 | Nuclear Engineering and Design |
| A simple novel analysis procedure for IVR calculation in core-molten severe accident | Zhang, Y., Qiu, S.*, Su, G.H., Tian, W. | 2011-12-30 | Nuclear Engineering and Design |
| Experimental research on transient critical heat flux in vertical tube under oscillatory flow condition | Zhao, D.W., Su, G.H*., Liang, Z.H., Zhang, Y.J., Tian, W.X., Qiu, S.Z | 2011-11-30 | International Journal of Multiphase Flow |
| Numerical investigation on coalescence of bubble pairs rising in a stagnant liquid | Chen, R.H., Tian, W.X., Su, G.H.*, Qiu, S.Z., Ishiwatari, Y., Oka, Y | 2011-11-30 | Chemical Engineering Science |
| Analysis of CHF in saturated forced convective boiling on a heated surface with impinging jets using artificial neural network and genetic algorithm | Cong, TL ; Chen, RH; Su, GH ; Qiu, SZ; Tian, WX | 2011-09-29 | Nuclear Engineering and Design |
| Study on the characteristic points of boiling curve by using wavelet analysis and genetic neural network | Wei H.M., Su G.H., Tian W.X., Qiu S.Z., Ni W.F. | 2009-12-27 | Nuclear Engineering and Design |
| Analysis on the neutron kinetics for a molten salt reactor | Zhang, DL. Qiu, SZ Su, GH Liu, C.L.Qian, L.B. | 2009-12-27 | Progress in Nuclear Energy |
| Development of a steady state analysis code for a molten salt reactor | Zhang DL, Qiu SZ, Su GH | 2009-12-27 | Annals of Nuclear Energy |
| Flow blockage analysis of a channel in a typical material test reactor core | Lu, Qing; Qiu, Suizheng; Su, G.H. | 2009-12-27 | Nuclear Engineering and Design |
| Experimental study on two-phase flow instability of natural circulation under rolling motion condition | Tan, Sichao; Su, G.H.; Gao, Puzhen | 2009-12-27 | Annals of Nuclear Energy |
| Heat transfer model of single-phase natural circulation flow under a rolling motion condition | Si-chao Tan; Su, G.H.; Pu-zhen, Gao | 2009-12-27 | Nuclear Engineering and Design |
| Experimental study on critical heat flux in bilaterally heated narrow annuli | Wu, Y.W.; Su, G.H.; Qiu, S.Z.; Hu, B.X. | 2009-12-27 | International Journal of Multiphase Flow |
| Theoretical research on two-phase flow instability in parallel channels | Zhang, Y.J.; Su, G.H.; Yang, X.B.; Qiu, S.Z. | 2009-12-27 | Nuclear Engineering and Design |
| Experimental and theoretical study on single-phase natural circulation flow and heat transfer under rolling motion condition | Tan, Si-chao; Su, G.H.; Gao, Pu-zhen | 2009-12-27 | Applied Thermal Engineering |
| Global attractivity and permanence of a SVEIR epidemic model with pulse vaccination and time delay | HM Wei; Y Jiang; XY Song; Su, GH; Qiu, SZ | 2009-12-27 | Journal of Computational and Applied Mathematics |
| 基于人工神经网络分析面朝下加热池式过渡沸腾 | 赵大卫; 苏光辉; 田文喜; 秋穗正; K. Sugiyama; | 2009-12-27 | 原子能科学技术 |
| 水平窄缝内多孔介质传热特性研究 | 扈本学; 徐彦峰; 苏光辉; 秋穗正; 赵大卫; 巫英伟; | 2009-12-27 | 原子能科学技术 |
| 基于小波分析和遗传算法的沸腾曲线特征点研究 | 魏会明; 苏光辉; 秋穗正; 杨杏波; | 2009-12-27 | 原子能科学技术 |
| 环形窄缝通道湍流流动换热特性分析 | 曾和义; 秋穗正; 苏光辉; | 2009-12-27 | 原子能科学技术 |
| 发展核电,任重道远 | 武春霞; 苏光辉; 朱继洲; | 2009-12-27 | 高科技与产业化 |
| 环形窄缝通道内干涸后摩擦倍增因子的试验研究 | 彭常宏; 秋穗正; 苏光辉; 贾斗南; | 2009-12-27 | 原子能科学技术 |
| 竖直矩形窄通道空气自然对流换热特性的实验研究 | 卢庆; 叶忠昊; 秋穗正; 苏光辉; | 2009-12-27 | 西安交通大学学报 |
| CARR热工水力与安全分析程序TSACC的开发与验证 | 田文喜; 秋穗正; 苏光辉; 贾斗南; 刘兴民; 张建伟; | 2009-12-27 | 核动力工程 |
| 板状燃料元件堆芯热工水力特性分析程序开发及验证 | 卢庆; 张志俭; 秋穗正; 苏光辉; 田文喜; | 2009-12-27 | 核动力工程 |
| 曲率对竖直向上环形狭窄通道内环状流特性的影响 | 杜东晓; 苏光辉; 秋穗正; | 2009-12-27 | 原子能科学技术 |
| 横摇条件下九通道系统两相流动不稳定性研究 | 张友佳; 苏光辉; 秋穗正; 郭玉君; | 2009-12-27 | 原子能科学技术 |
| 新概念熔盐堆的固有安全性及相关关键问题研究 | 秋穗正, 张大林, 苏光辉, | 2009-12-27 | 原子能科学技术 |
| Development of a safety analysis code for molten salt reactors | Dalin Zhang, Suizheng Qiu, Guanghui Su | 2009-12-27 | Nuclear Engineering and Design |
| Global attractivity and permanence of a delayed SVEIR epidemic model with pulse vaccination and saturation incidence | Y Jiang,HM Wei,XY Song,LQ Mei,GH Su,SZ Qiu | 2009-12-27 | Applied Mathematics and Computation |
| Development of a thermal–hydraulic analysis code for research reactors with plate fuels | Qing Lu, Suizheng Qiu, G.H. Su | 2009-12-27 | Annals of Nuclear Energy |
| 出版物 | 作者 | 出版日期 | 出版社 |
|---|---|---|---|
| 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 |
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