苏光辉教授




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

 
     ►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。

论文期刊

没有找到条目。
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

出版物

没有找到条目。
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