Osamong Gideon Akou, Xuan Wang, Shuhuan Liu, Xin-Wei Liu, Guanghui Su, Ai-Ling Zhang, Junfang Zhang, Minghua Lv, Lei Huang, Shanchao Yang (2026). Atmospheric dispersion and ecological risk assessment of hypothetical accidents at Kenya's first proposed nuclear power plant. Progress in nuclear energy (New series).DOI
Xin-Kun Xiao, Q. Cai, Tian-Rui Li, Rong-Hua Chen, Guanghui Su (2026). Uncertainty analysis framework of MPS and implementation in the simulation of MCCI phenomenon. Computers and Mathematics with Applications.DOI
P. Ou, Yong-Zheng Chen, Peng Chen, Yong Ouyang, Chao Guo, Guanghui Su (2026). Uncertainty and sensitivity analysis of containment aerosol removal under severe accident. Progress in nuclear energy (New series).DOI
Wen Zhibo, Li Xinyu, D H Zhang, Qiao Pengrui, Wenxi Tian, Suizheng Qiu, Su Guanghui (2026). Theoretical and numerical study on discontinuous Galerkin flux reconstruction method in thermal-hydraulic analysis. Annals of Nuclear Energy.DOI
Jian Wu, Wenxiang Gao, Mingjun Wang, Kailun Guo, Guanghui Su (2026). Modeling and control strategy of nuclear power plant based on heat pipe reactor and Brayton cycle system. Annals of Nuclear Energy.DOI
Xingguang Zhou, Dalin Zhang, Xinyu Li, Wentao Ma, Hongxing Yu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2026). Flow organization in unstably stratified mixed convection at Ri = 1 for heavy liquid metals. Physical Review Fluids.DOI
J Z Zhao, Liangguo Li, Jing Zhang, Jiyong Liu, Guorui Yang, Yingwei Wu, Guanghui Su, Wenxi Tian (2026). Study on flow dynamics and phase transition characteristics of two-phase ejection in confined small channels. Physics of Fluids.DOI
Yin Zhang, Zeqin Zhang, Chenglong Wang, Kailun Guo, Wenxi Tian, Guanghui Su, Suizheng Qiu (2026). Geometric design optimization and application of three-stage segmented thermoelectric generators in heat pipe reactor. Applied Thermal Engineering.DOI
Ruiyu Han, Shaopeng He, Ruijie Wang, Zili Gong, Mingjun Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2026). Numerical study of flow-induced vibration in heat transfer tubes of shell-and-tube heat exchangers under ocean conditions. Progress in Nuclear Energy.DOI
Hongquan Liu, Yuhang Niu, Yingwei Wu, Yanan He, Chuan Lu, Guanghui Su (2026). Thermal-fluid-structure interaction modeling and experimental investigation of thermal deformation in the water-cooled parallel plate assembly. Applied Thermal Engineering.DOI
Jingyu Nie, Junqiang Zheng, Yingwei Wu, Yanan He, Jing Zhang, Guoliang Zhang, Qisen Ren, Guanghui Su (2026). Comsol-based nuclear-thermal coupling methodology and its application in microreactors. Annals of Nuclear Energy.DOI
Jiarui Zhang, Yuankun Mou, Kailun Guo, Zihao Hei, Chenglong Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2026). Investigation of heat transfer behavior of high-temperature heat pipes under transient input power conditions. Applied Thermal Engineering.DOI
Liaojie Deng, Dalin Zhang, Xinyu Li, Yuehua Chen, Lei Zhou, Wenxi Tian, Suizheng Qiu, Guanghui Su (2026). Development of delayed neutron precursor and decay heat models for molten salt reactors using runge–kutta discontinuous Galerkin methods. Applied Thermal Engineering.DOI
Huifang Zhang, Jian Yu, Yapei Zhang, Shihao Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2026). Study on hydrodynamic characteristics of symmetric two-droplet impact on film using lattice Boltzmann method. Progress in Nuclear Energy.DOI
Yangbin Deng, Zijian Huang, Cong Liu, Ruikuan Li, Yue Wu, Yingwei Wu, Guanghui Su (2026). Upgrade of FROBA code to derive new insights in fuel performance of Lead-Bismuth Eutectic Cooled Fast Reactor. Progress in Nuclear Energy.DOI
Chunjie Zeng, Defang Mu, Hanrui Qiu, Mingjun Wang, Ge Ping Wu, Wenxi Tian, Guanghui Su (2026). High-fidelity full-scale three-dimensional thermal-hydraulic characteristics analysis of the primary and secondary side in a steam generator. International Journal of Thermal Sciences.DOI
Q. Zhang, N Chen, Shiqi Wang, Mengdi Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2026). Numerical Study of Aerosol Deposition in Micro-channel Based on Openfoam. Springer proceedings in physics.DOI
Jie Rong, Mengdi Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2026). Study on the Trajectory of Foreign Objects on the Secondary Side of Nuclear Power Steam Generator. Springer proceedings in physics.DOI
S Wang, Mingjun Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2026). Characterization of Bubble Motion in Bottom Submerged Orifice Under Rolling Conditions. Springer proceedings in physics.DOI
Xinhang Peng, Tian Zhang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2026). MYRRHA Fast Reactor Am-Bearing Fuel Pins Modelling Using OFFBEAT. Springer proceedings in physics.DOI
Osamong Gideon Akou, Xuan Wang, Shuhuan Liu, Xin-Wei Liu, Guanghui Su, Ai-Ling Zhang, Junfang Zhang, Minghua Lv, Lei Huang, Shanchao Yang (2025). Impact of community shielding on radiological risk following a hypothetical nuclear explosion. Nuclear Engineering and Design.DOI
Gideon Akou Osamong, Xuan Wang, Shuhuan Liu, Xin-Wei Liu, Guanghui Su, Ai-Ling Zhang, Junfang Zhang, Minghua Lv, Lei Huang, Shanchao Yang (2025). Tritium dispersion analysis using HotSpot code: a comparative study across reactor types and environmental conditions. Journal of Radiological Protection.DOI
Osamong Gideon Akou, Xuan Wang, Shuhuan Liu, Xin-Wei Liu, Guanghui Su, Ai-Ling Zhang, Junfang Zhang, Minghua Lv, Lei Huang, Shanchao Yang (2025). Parametric Analysis of Radiological Impact from Hypothetical Accident Scenario at the Sanmen Nuclear Power Plant. Nuclear Technology.DOI
J.H. Wang, Jinyuan Wang, Panxiao Li, Chenglong Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu (2025). Numerical investigation of high-temperature heat pipe bundle failure scenario for heat pipe cooled reactor. Progress in Nuclear Energy.DOI
Jing Zhang, Mingjun Wang, Wenxi Tian, Yingwei Wu, Guanghui Su, Suizheng Qiu (2025). Intelligent optimization and evaluation techniques for thermal-hydraulic safety analysis of nuclear power systems. Chinese Science Bulletin (Chinese Version).DOI
H.-C. Zhang, Yapei Zhang, Shihao Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). Highly accurate and interpretable machine learning models for predicting HTC in the presence of NCG on outer vertical tubes. Progress in Nuclear Energy.DOI
Zhuofan Li, Changzhong Li, Chenglong Wang, Yanyu Sun, Dingsheng S. Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu (2025). Experimental investigation of heat transfer and friction characteristics of high-pressure helium with variable properties in circular tubes. International Journal of Thermal Sciences.DOI
Lifan Zhao, Mingjun Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). Numerical Simulation of Foreign Object Motion on Secondary Side of Steam Generator Tube Zone. Springer proceedings in physics.DOI
Yue Lin, Dalin Zhang, Yuzhuo Cai, Yapeng Liu, Peng Du, Pengrui Qiao, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). Numerical study on material behavior and core temperature field evolution under CDAs in LFR. Nuclear Engineering and Technology.DOI
Xingguang Zhou, Dalin Zhang, Xinyu Li, Hongxing Yu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). Mixed convection in horizontal channel with unstable stratification for low-Prandtl-number fluids. Physics of Fluids.DOI
Xin Yu, Zeqin Zhang, Xiaoyan Wang, Tianyuan Liu, Kailun Guo, Haocheng Zhao, Chunping Tian, Mingjun Wang, Suizheng Qiu, Guanghui Su, Wenxi Tian (2025). Deep learning-based model for predicting physical fields during frozen startup of high-temperature heat pipes. International Journal of Thermal Sciences.DOI
Defang Mu, Chunjie Zeng, Hanrui Qiu, Mingjun Wang, Hang Zang, Kailun Guo, Wenxi Tian, Guanghui Su (2025). Study on the flashing-induced deposition in steam generator tube support plate. Physics of Fluids.DOI
Chunjie Zeng, Hanrui Qiu, Mingjun Wang, Kailun Guo, Jing Zhang, Wenxi Tian, Guanghui Su (2025). Development of STEAM code: a steam generator tube-level three-dimensional thermal–hydraulic analysis platform. Nuclear Engineering and Design.DOI
Xingguang Zhou, Dalin Zhang, Xinyu Li, Wentao Guo, Hongxing Yu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). Mean flow characteristics in horizontal and vertical channels with unstable stratification by buoyancy for liquid lead. European Journal of Mechanics - B/Fluids.DOI
Yue Lin, Dalin Zhang, Yuzhuo Cai, Yapeng Liu, Peng Du, Zhixin Niu, Bo Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). Numerical study on influence of LFR water-cooled reactor vessel cooling system under unprotected loss of heat sink Accident. Progress in Nuclear Energy.DOI
Z.X. Zhang, Xue Meng, Yugao Ma, Kailun Guo, Shuhua Ding, Chenglong Wang, Xiaoming Chai, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). Experimental study of heat transfer characteristics of bent high-temperature heat pipe. International Journal of Thermal Sciences.DOI
Jian Hui Zhao, Jing Zhang, Yingwei Wu, Guanghui Su, Wenxi Tian, Suizheng Qiu (2025). Analysis of three-dimensional flow field and reactor vessel impact failure in sodium-cooled fast reactor core disruptive accident. Applied Thermal Engineering.DOI
Zeqin Zhang, Chenglong Wang, Jinlu Huang, Kailun Guo, Wenxi Tian, Guanghui Su, Suizheng Qiu (2025). Preliminary design and assessment of the residual heat removal system in a nuclear silent heat pipe-cooled reactor. International Journal of Thermal Sciences.DOI
Zhifan Zhou, Jing Zhang, Yingwei Wu, Mingjun Wang, Yanan He, Kailun Guo, Chenglong Wang, Guanghui Su, Wenxi Tian, Suizheng Qiu (2025). Study of thermo-mechanical failure mechanisms of fuel assemblies for gas-cooled space nuclear propulsion system. Journal of Thermal Stresses.DOI
Xingguang Zhou, Da‐Lin Zhang, Xinyu Li, Hongxing Yu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). DNS study of turbulent heat transfer with different Prandtl numbers under constant wall-temperature difference condition. Progress in Nuclear Energy.DOI
Zeqin Zhang, Zhipeng Zhang, Chenglong Wang, Kailun Guo, Wenxi Tian, Guanghui Su, Suizheng Qiu (2025). Heat pipe-cooled reactors: A comprehensive review of evolution, challenges, research status, and outlook. Renewable and Sustainable Energy Reviews.DOI
Zhenyu Feng, Dalin Zhang, Wenqiang Wu, Haodong Guo, Xilin Zhang, Xiaoyu Wang, Jian Deng, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). Numerical study on the thermal stratification characteristics of the primary system for Lead-based cooled Fast Reactor. Nuclear Engineering and Technology.DOI
Yan Zhang, Yan Zhang, Bo Wang, Dalin Zhang, Chenglong Wang, Yang Yang, Zhengrong Guo, Wenxi Tian, Guanghui Su, Suizheng Qiu (2024). Coupled analysis of oxidation corrosion and heat transfer in lead-cooled fast reactors. Annals of Nuclear Energy.DOI
Haocheng Zhao, Chenglong Wang, Suizheng Qiu, Wenxi Tian, Guanghui Su (2024). Thermo-electric characteristics analysis of thermionic energy conversion in space nuclear reactors. Applied Thermal Engineering.DOI
Yue Lin, Dalin Zhang, Yutong Chen, Xisi Zhang, Jian Deng, Peng Du, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Numerical study on the impact characteristics of molten lead-bismuth droplets into water. Nuclear Engineering and Design.DOI
Lei Zhou, Dalin Zhang, Yapeng Liu, Liang Yu, Bo Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Direct numerical simulation of sodium in vertical channel flow: From forced convection to natural convection at friction Reynolds number 180. Physics of Fluids.DOI
Wenxi Tian, Jiarui Zhang, Chenglong Wang, Kailun Guo, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Design, fabrication, and comparative analysis of prototype high-temperature heat pipes charged with sodium for heat pipe cooled reactor NUSTER-100. Applied Thermal Engineering.DOI
Haocheng Zhao, Zeqin Zhang, Chenglong Wang, Suizheng Qiu, Wenxi Tian, Guanghui Su (2024). Operation characteristics analysis of high temperature alkali metal heat pipe based on OpenFOAM. Applied Thermal Engineering.DOI
Zichao Han, Jing Zhang, Mingjun Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu (2024). Steady-state thermal–hydraulic analysis of an NTP reactor core based on the porous medium approach. Annals of Nuclear Energy.DOI
Qifan Yu, Hongjian Guo, Suizheng Qiu, Chenglong Wang, Dalin Zhang, Wenxi Tian, Guanghui Su (2024). Separate effect experimental test and theoretical investigate of pressure wave propagation and pressure rising process upon SGTR accident in advanced LFRs. Nuclear Engineering and Design.DOI
Shuowang Fan, Yutong Chen, Dalin Zhang, Jian Deng, Xisi Zhang, Xiaoli Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Experimental study on fragmentation characteristics of molten stainless steel discharged into liquid Lead-Bismuth Eutectic pool. Annals of Nuclear Energy.DOI
Kailun Guo, Qishi Sun, Hao Xuan Sun, Chenlong Wang, Kang Chen, Wenxi Tian, Guanghui Su, Suizheng Qiu (2024). Numerical Investigation of High-Temperature Heat Pipes With Different Wick Structures Under Non-Uniform Heating Boundary Conditions.DOI
Zhengyang Dong, Kai Liu, Mingjun Wang, Junmei Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Development of Two-Dimensional Heat Conduction Model in Subchannel Code Based on OpenFOAM.DOI
Chen Qingshan, Mingjun Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Multi-Objective Optimization Study of Nozzle Outlet Size Based on Atomization Performance.DOI
Jian Hui Zhao, Jing Zhang, Yingwei Wu, Guanghui Su, Wenxi Tian, Suizheng Qiu (2024). Numerical Analysis of Three-Dimensional Flow Field Impact Under Strong Transient Conditions in Advanced Reactors.DOI
Zhipeng Zhang, Chenglong Wang, Kailun Guo, Wenxi Tian, Guanghui Su, Suizheng Qiu (2024). Study of Gravity Effect on the Operating Characteristics of High-Temperature Bent Heat Pipes.DOI
Guorui Yang, Jing Zhang, Yingwei Wu, Yanan He, Suizheng Qiu, Guanghui Su, Wenxi Tian (2024). Experimental Study of Bubble Migration Characteristics in MCCI Molten Pool.DOI
Ji Zhang, Mingjun Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Study of Jet Characteristics and Structural Fatigue in the Upper Chamber of a Lead-Bismuth Eutectic Cooled Reactor Based on Fluid-Structure Coupling Methods.DOI
Wenqiang Wu, Dalin Zhang, Tao Huang, Lei Zhou, Peng Du, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Development and Validation of a Two-Phase Flow Solver With Drift-Flux Model Based on OpenFOAM.DOI
Defang Mu, Jie Rong, Mingjun Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Investigating the Motion Characteristics of Complex-Shaped Foreign Objects on the Secondary Side of a Steam Generator Based on CFD-DEM Method.DOI
Xinze Li, Ronghua Chen, Bingqian Zhang, Kui Zhang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Preliminary Study on Laser Inertial Confinement Fusion Reactor Energy Transfer.DOI
Shuo Liu, Chenglong Wang, Suizheng Qiu, Wenxi Tian, Guanghui Su (2024). Temperature Field Rapid Estimation of Space Nuclear Thermionic Reactor Based on Reduced-Order Model.DOI
Menghao Luo, Zhiwei Lü, Yanan He, Yingwei Wu, Wenxi Tian, Guanghui Su, Suizheng Qiu (2024). Study on Heat Transfer Characteristics of 2×2 Helical Cruciform Fuel Assembly Under Non-Uniform Heat Source.DOI
Shuowang Fan, Yutong Chen, Dalin Zhang, Xiaoli Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Numerical Study on Molten Stainless Steel and Lead Bismuth Eutectic Interaction for Lead-Cooled Fast Reactors Using the ACENA Code With Experimental Validation.DOI
Chenglong Wang, Chenglong Wang, Chen Wang, Chen Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu (2024). Code development and preliminary validation for lead-cooled fast reactor thermal-hydraulic transient behavior. Nuclear Engineering and Technology.DOI
Xindi Lv, Dalin Zhang, Xinyu Li, Xingguang Zhou, Dianqiang Jiang, Guanghui Su, Wenxi Tian, Suizheng Qiu (2024). Study on the safety characteristics of fluoride-salt-cooled high-temperature advanced reactor. Annals of Nuclear Energy.DOI
Zeqin Zhang, Chenglong Wang, Chao Tan, Kailun Guo, Guanghui Su, Wenxi Tian, Suizheng Qiu (2023). Investigation of neutronic and thermal–electric coupling phenomenon in a 100 kWe-level nuclear silent heat pipe-cooled reactor. Applied Thermal Engineering.DOI
Lei Zhou, Dalin Zhang, Shibao Wang, Yapeng Liu, Liang Yu, Jing Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2023). Benchmark analysis of the FFTF LOSWOS test #13 with OpenMC and THACS. Annals of Nuclear Energy.DOI
Yingjie Wang, Zhixian Lai, Hanrui Qiu, Mingjun Wang, Wenxi Tian, Guanghui Su (2023). Experimental and numerical analysis of the liquid metal mixing phenomenon in complex jets of Gen-IV nuclear system. International Journal of Heat and Mass Transfer.DOI
Xingguang Zhou, Dalin Zhang, Jie Liu, Chao Lin, Liang Yu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2023). Numerical and experimental analysis of LBE flow and heat transfer characteristics in hexagonal rod bundles. Annals of Nuclear Energy.DOI
Kailun Guo, Yin Zhang, Xingyang Lin, Jinlu Huang, Chenglong Wang, Suizheng Qiu, Wenxi Tian, Guanghui Su (2023). Transient thermoelectric characteristics of the principle prototype for the heat pipe cooled nuclear Silent themoelectirc reactor (NUSTER). Annals of Nuclear Energy.DOI
Yuliang Fang, Qifan Yu, Chenglong Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu (2023). Heat transfer of hydrogen with variable properties in a heated tube. International Journal of Heat and Mass Transfer.DOI
Liangguo Li, Jianming Yu, Zongbao Nan, Donghua Lu, Jun Xing, Xianghui Lu, Yingwei Wu, Suizheng Qiu, Guanghui Su, Wenxi Tian, Xiaohang Wu, Jiyong Liu (2023). Experimental research and theoretical analysis of flow instability in advanced secondary passive residual heat removal system. Annals of Nuclear Energy.DOI
Zheng Junqiang, Yanan He, Junmei Wu, Yingwei Wu, Yuanming Li, Wenxi Tian, Guanghui Su, Suizheng Qiu (2023). THE DEVELOPMENT OF FISSION PRODUCT DIFFUSION/RELEASE MODEL FOR FAILED TRISO PARTICLES. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Ruiyu Han, Zetao Wang, Kailun Guo, Chenglong Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). Experimental investigation of nano-particle deposited wick Structure's heat transfer characteristics. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
Zhipeng Liu, Yafeng Zhao, Chenglong Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). Experimental study on heat transfer characteristics of LBE flow in a vertical tube under static and rolling conditions. International Journal of Heat and Mass Transfer.DOI
Hao Sun, Marco Pellegrini, Chenglong Wang, Shunichi Suzuki, Koji Okamoto, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). CFD simulation based on film model of high temperature potassium heat pipe at different positions: Horizontal, vertical, and 45° inclined. Progress in Nuclear Energy.DOI
Zehua Ma, Ren Liang, Zhikang Lin, Yong Ouyang, Xianghui Lu, Guanghui Su (2022). Numerical Simulation of Fuel Relocation at High Burnup With Discrete Element Method.DOI
Hongquan Liu, Yanan He, Yingwei Wu, Guanghui Su, Wenxi Tian, Suizheng Qiu (2022). Preliminary Development of a Coupling Environment Based on MOOSE and OpenFOAM and Its Application on Plate Fuel Modeling. Volume 15: Student Paper Competition.DOI
Chunjie Zeng, Mingjun Wang, Ge Ping Wu, Shasha Yin, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). Numerical study on the enhanced heat transfer characteristics of steam generator with axial economizer. International Journal of Thermal Sciences.DOI
Mingjun Wang, Linfeng Li, Kai Liu, Jing Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). Development of subcooled wall boiling model considering bubble sliding in narrow rectangular channel. International Journal of Thermal Sciences.DOI
Yingjie Wang, Mingjun Wang, Jia Kang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). Thermal fatigue analysis of structures subjected to liquid metal jets at different temperatures in the Gen-IV nuclear energy system. Energy.DOI
Yuliang Fang, Chenglong Wang, Wenxi Tian, Dalin Zhang, Guanghui Su, Suizheng Qiu (2022). Study on high-temperature hydrogen dissociation for nuclear thermal propulsion reactor. Nuclear Engineering and Design.DOI
Jiatong Tan, Quan Li, Bo Zhao, Chao Ma, Yingwei Wu, Yuanming Li, Jing Zhang, Yanan He, Tianzhou Ye, Cheng Zhang, Wenxi Tian, Guanghui Su, Suizheng Qiu (2021). Multi-Objective Optimization Design of Plate-type Fuel via Co-simulation Method. Annals of Nuclear Energy.DOI
Chen Wang, Chenglong Wang, Yan Zhang, Dalin Zhang, Wenxi Tian, Guanghui Su, Suizheng Qiu (2021). Flow and heat transfer evaluation of lead-bismuth eutectic coolant for nuclear power application. Nuclear Engineering and Design.DOI
Zhao Xin Jin, Chenglong Wang, Xiao Liu, Zhiwen Dai, Wenxi Tian, Guanghui Su, Suizheng Qiu (2021). Operation and safety analysis of space lithium-cooled fast nuclear reactor. Annals of Nuclear Energy.DOI
Liangguo Li, B. Long, Jianming Yu, Qianhua Su, Donghua Lu, Yingwei Wu, Suizheng Qiu, Guanghui Su, Wenxi Tian, Xiaohang Wu, Jiyong Liu, Peng Ju (2021). Research on scaling analysis and design parameters of integral test facilities for PWR. Annals of Nuclear Energy.DOI
Irfan Khan, Mingjun Wang, Yapei Zhang, Wenxi Tian, Guanghui Su, Suizheng Qiu (2020). Two-phase bubbly flow simulation using CFD method: A review of models for interfacial forces. Progress in Nuclear Energy.DOI
Kaiqiang Wang, Hongen Chen, Pengpeng Shi, Lijuan Li, Shejuan Xie, Zhenmao Chen, Baoping Hei, Fu‐Hai Gao, Hongyi Yang, Yingwei Wu, Guanghui Su (2020). Measurement method for deformation and contact force of the fuel assembly for China fast reactor under thermal gradient. Annals of Nuclear Energy.DOI
Zhiwen Dai, Chenglong Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2019). Thermoelectric characteristics analysis of thermionic space nuclear power reactor. International Journal of Energy Research.DOI
Hao Sun, Chenglong wang, Pan Ma, Xiao Liu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2018). Conceptual design and analysis of a multipurpose micro nuclear reactor power source. Annals of Nuclear Energy.DOI
Peiwei Sun, Huanhuan Zhao, Longtao Liao, Jianmin Zhang, Guanghui Su (2017). Control system design and validation platform development for small pressurized water reactors (SPWR) by coupling an engineering simulator and MATLAB/Simulink. Annals of Nuclear Energy.DOI
苏光辉（2016）. 轻水堆核电厂严重事故现象学 = Severe accident phenomenology of light water reactors. 《国防工业出版社》.
Rui Zhang, Rong Hua Chen, Wen Tian, Guang Hui Su, Suizheng Qiu (2015). Analysis of AP1000 ex-vessel steam explosion behavior using TEXAS-V code. Energy science and technology.DOI
Yao Xiao, Lin-Wen Hu, Suizheng Qiu, Dalin Zhang, Su Guanghui, Wenxi Tian (2014). Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor. Journal of Nuclear Engineering and Radiation Science.DOI
Wei Li, Xiaoli Wu, Dalin Zhang, Guanghui Su, Wenxi Tian, Suizheng Qiu (2014). Preliminary study of coupling CFD code FLUENT and system code RELAP5. Annals of Nuclear Energy.DOI
Xiaoli Wu, Yapei Zhang, Wenxi Tian, Guanghui Su, Suizheng Qiu (2014). Analysis of a Loss of Heat Removal Accident in a PWR Spent Fuel Pool.DOI
Xin Li, Wen Tian, Rong Hua Chen, Lai Shun Wang, Guang Hui Su, Suizheng Qiu (2013). Numerical simulation of Taylor bubble rising in liquid lead-bismuth eutectic based on MPS method. Energy science and technology.DOI
Zaiyong Ma, Zicheng Qiu, Yingwei Wu, Suizheng Qiu, Guanghui Su (2013). An analysis of incipient boiling superheat in alkali liquid metals. International Journal of Heat and Mass Transfer.DOI
Xinli Gao, Tiejun Zu, Wenxi Tian, Suizheng Qiu, Guanghui Su, Hong‐Chun Wu (2013). Thermal-hydraulic design of water-cooled pressure tube blanket for a fusion driven subcritical reactor. Fusion Engineering and Design.DOI
Zhike Lan, Dahuan Zhu, Wenxi Tian, Guanghui Su, Suizheng Qiu (2013). Numerical approaches and analysis of spray characteristics for pressuriser nozzles. The Canadian Journal of Chemical Engineering.DOI
Yali Su, Jian Feng, Hao Jiang Zhao, Wenxi Tian, Guanghui Su, Suizheng Qiu (2013). Theoretical study on the flow instability of supercritical water in the parallel channels. Progress in Nuclear Energy.DOI
Zhen Hui Liang, Yan Fei Wen, Chao Gao, Wen Tian, Yingwei Wu, Guang Hui Su, Suizheng Qiu (2012). Experimental investigation on flow and heat transfer characteristics of single-phase flow with simulated neutronic feedback in narrow rectangular channel. Nuclear Engineering and Design.DOI
Zaiyong Ma, Yingwei Wu, Zicheng Qiu, Wenxi Tian, Guanghui Su, Suizheng Qiu (2012). An innovative method for prediction of liquid metal heat transfer rate for rod bundles based on annuli. Annals of Nuclear Energy.DOI
Juan Li Zuo, Wen Tian, Suizheng Qiu, Rong Hua Chen, Guang Hui Su (2011). Numerical simulation on single bubble rising behavior in liquid metal using moving particle semi-implicit method. Energy science and technology.
Rong Hua Chen, Wen Tian, Juan Li Zuo, Guang Hui Su, Suizheng Qiu (2011). Numerical investigation on bubble condensation and coalescence of bubble pairs using moving particle semi-implicit method. Journal of Engineering Thermophysics.
Rong Hua Chen, Wen Tian, Juan Li Zuo, Guang Hui Su, Suizheng Qiu, Jian Hui Xu (2011). Numerical analysis of bubble rising behavior in a liquid metal using MPS.
Rong Hua Chen, Wen Tian, Guang Hui Su, Suizheng Qiu (2011). Numerical simulation on bubble growth and departure by MPS. Energy science and technology.
Rong Hua Chen, Guang Hui Su, Suizheng Qiu (2010). Study on Pool Boiling and Flow Boiling with Artificial Neural Networks. Hedongli gongcheng.
Weifeng Ni, Suizheng Qiu, Guanghui Su, Wenxi Tian (2010). Preliminary Analysis of Three ULOFAs Based on the Dual-Functional Lithium Lead Test Blanket Module Configuration in ITER. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Junli Gou, Suizheng Qiu, Guanghui Su, Jia Dounan (2009). Thermal Hydraulic Analysis of a Passive Residual Heat Removal System for an Integral Pressurized Water Reactor. Science and Technology of Nuclear Installations.DOI
Wenxi Tian, Suizheng Qiu, Guanghui Su, Jia Dounan, Xingmin Liu, Jianwei Zhang (2007). Thermohydraulic and safety analysis on China advanced research reactor under station blackout accident. Annals of Nuclear Energy.DOI
Yingwei Wu, Guanghui Su, Suizheng Qiu, Ken-ichiro SUGIYAMA (2007). ICONE15-10388 NUMERICAL SIMULATION OF NATURAL CONVECTION HEAT TRANSFER FROM A DOWNWARD-FACING HORIZONTAL ROUND PLATE IN CONFINED SPACE. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Dalin Zhang, Suizheng Qiu, Guanghui Su, Jia Dounan (2007). ICONE15-10451 Evaluation of Static Thermodynamic Properties of the Ternary Molten Salt System Li, Na, Be/F, Based on the Modified Peng-Robinson Equation. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Ken-ichiro SUGIYAMA, Hiroomi AOKI, Guanghui Su, Yoshihiro KOJIMA (2005). Experimental Study on Coolability of Particulate Core-Metal Debris Bed with Oxidization, (I) Fragmentation and Enhanced Heat Transfer in Zircaloy-50 wt%Ag Debris Bed. Journal of Nuclear Science and Technology.DOI
Suizheng Qiu, Minoru Takahashi, Jia Dounan, Guanghui Su (2003). Density Wave Instability of Sodium Boiling Two-phase Flow in a Vertical Annulus at Low Pressure. Journal of Nuclear Science and Technology.DOI
Guanghui Su, Kenji Fukuda, Koji Morita, Mark Pidduck, Jia Dounan, Tatsuya Matsumoto, Ryo Akasaka (2002). Applications of Artificial Neural Network for the Prediction of Flow Boiling Curves. Journal of Nuclear Science and Technology.DOI
Guanghui Su, Kenji FUKUDA, Jia Dounan, Koji Morita (2002). Application of an Artificial Neural Network in Reactor Thermohydraulic Problem: Prediction of Critical Heat Flux. Journal of Nuclear Science and Technology.DOI
Suizheng Qiu, Minoru Takahashi, Jia Dounan, Guanghui Su (2001). K-2206 Experimental Study on Heat Transfer of Boiling Two-Phase Flow in Narrow Annular Channel. The proceedings of the JSME annual meeting.DOI
Xingchen Yan, Kai Liu, Xitong Liu, Mingjun Wang, Hanrui Qiu, Mengjiao Feng, Dahuan Zhu, Wenxi Tian, Guanghui Su (2026). The Mechanisms of Flow Migration and Thermal Redistribution of Inert Binary Gas Mixtures in 61-Pin Wire-Wrapped Rod Bundles. SSRN Electronic Journal.DOI
Ruibo Zhang, Zichao Han, Kailun GUO, Mingjun Wang, Hanrui Qiu, Yongquan Li, Guanghui Su (2026). Tree-like self-supporting fins for additively manufactured compact heat exchangers: configuration design and CFD analysis. SSRN Electronic Journal.DOI
Lingyi Zhang, Wenxi Tian, Zhou Peide, Yang Yong, Yufeng Lyu, Suizheng Qiu, Guanghui Su (2025). Scaling Methodology and Transient Distortion Evaluation For Loop-Type Sodium-Cooled Fast Reactors. SSRN Electronic Journal.DOI
HUSSAINI MUHAMMAD, Guanghui Su, Xuan Wang, Mingjun Wang (2025). Estimation of the Offsite Radiological Doses and Epzs Sizes for Major Ap1000 Containment Releases Using Rascal Atdm. SSRN Electronic Journal.DOI
HUSSAINI MUHAMMAD, Guanghui Su, Xuan Wang, Mingjun Wang (2025). Early Phase Acute Exposure Dose Assessment of a Postulated Nuclear Accident Under the Most Influential Weather Conditions Using the Hotspot Program. SSRN Electronic Journal.DOI
Yang Wang, Xinyu Li, Dalin Zhang, Bin Wang, Pengrui Qiao, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). Simulation of Supercritical Carbon Dioxide Jet Based on RK-DGSEM Numerical Method. SSRN Electronic Journal.DOI
Zimian Duan, Jing Zhang, Yingwei Wu, Mingjun Wang, Yanan He, Guanghui Su (2025). Analysis of Multi-physics Coupling Behavior of BeO-%UO2 Co-sintered Dispersion Fuel. SSRN Electronic Journal.DOI
Jinshun Wang, Ronghua Chen, Liang Yu, Minyang Gui, Xinyang Zhu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Development, Validation and Application of Sub-Channel Thermal-Hydraulic Analysis Code for Liquid Metal Cooled Reactor. SSRN Electronic Journal.DOI
Changzhong Li, Chenglong Wang, Yanyu Sun, Ronghua Chen, Wenxi Tian, Guanghui Su, Suizheng Qiu (2024). Experimental Investigation on Flow and Heat Transfer Characteristics of Helium in Rectangular Narrow Slit Channel. SSRN Electronic Journal.DOI
Yiwen Chen, Dalin Zhang, Dianqiang Jiang, Wei Li, Xiaoli Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Thermal-Mechanical Influence Aspects and Evaluation of Helical Cruciform Single Rod in Fluoride-Salt-Cooled High-Temperature Advanced Reactor. SSRN Electronic Journal.DOI
Zhang Yin, Kailun Guo, Chenglong Wang, Jing Lin Zhang, Yulu Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu (2024). Research on Artificial Neural Network for Geometric Design and Optimization of Three-Stage Segmented Thermoelectric Generators. SSRN Electronic Journal.DOI
Haoyang LI, Dalin Zhang, Lei Zhou, Jian Deng, Wenxi Tian, Guanghui Su, Suizheng Qiu (2024). Numerical Study on Benchmark Analysis of Nacie-Up Facility with Uniform and Non-Uniform Power Distribution. SSRN Electronic Journal.DOI
Ruiyu Sun, Jianjun Wang, Jinshun Wang, Ronghua Chen, Xing Yu Jiang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2023). Sacos-Plate: A New Thermal-Hydraulic Subchannel Analysis Code for Plate Type Fuel Assemblies. SSRN Electronic Journal.DOI
Dalin Zhang, Xinyu Li, Dianqiang Jiang, Xingguang Zhou, Xindi Lv, Shichang YUN, Wenqiang Wu, Xuanang He, Haoyang LI, Xin Min, Kailong Chen, Wenxi Tian, Suizheng Qiu, Guanghui Su, Quanbin Zhao, Yao Fu, Chuntao TANG, Wenbin Zhuo, Jinggang LI, Zuo Jiaxu (2023). Fluoride-Salt-Cooled High-Temperature Reactor: An Integrated Nuclear-Based Energy Production and Conversion System. SSRN Electronic Journal.DOI
Yapeng Liu, Dalin Zhang, Lei Zhou, Kailong Chen, Wenxi Tian, Suizheng Qiu, Guanghui Su (2023). Analysis of the Effect of Thermal Stratification on the Natural Cycle Decay Heat Removal of Sodium-Cooled Fast Reactor. SSRN Electronic Journal.DOI
Jianghan Fu, Jin Hao Zhao, Zhiwen Dai, Guanghui Su, Chenglong Wang, Wenxi Tian, Suizheng Qiu (2023). Model Predictive Control for Automatic Operation of Space Nuclear Reactors: Design, Simulation, and Performance Evaluation. SSRN Electronic Journal.DOI
Shuo Liu, Jin Zhao, Chenglong Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su, Jun Yang (2023). Dynamic Modeling of Steam Power Conversion System in Sodium-Cooled Fast Reactor. SSRN Electronic Journal.DOI
Shuo Liu, Jin Zhao, Chenglong Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su, Jun Yang (2023). Development and Verification of Safety Analysis Code to Model and Simulate Steam Power Conversion System in Sodium-Cooled Fast Reactor. SSRN Electronic Journal.DOI
Xinyu Li, Dalin Zhang, Shichang YUN, Xingguang Zhou, Dianqiang Jiang, Xindi LV, Zhenyu Feng, Wenqiang Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su, Quanbin Zhao, Xiuting LIU (2022). Design and Optimal Thermal Efficiency Contrastive Analysis on Closed Brayton Cycle Systems with Different Fluids of Fluoride-Salt-Cooled High-Temperature Advanced Reactor. SSRN Electronic Journal.DOI
Xingguang Zhou, Dalin Zhang, Xinyu Li, Wenxi Tian, Guanghui Su, Suizheng Qiu (2022). High-Fidelity Neutronics and Thermal-Hydraulics Analysis of Helical Cruciform Fuel Based on Small Modular Fhr. SSRN Electronic Journal.DOI
Xindi LV, Dalin Zhang, Gongle Song, Guanghui Su, Wenxi Tian, Suizheng Qiu (2022). Experimental Study on Flow Patterns in Narrow Rectangular Channels. SSRN Electronic Journal.DOI
Yugao Ma, Xueqing Wang, Hongxing Yu, Shanfang Huang, Yingnan Zhang, Jian Huang, Guanghui Su, Jian Deng, Xiaoming Chai, Wenzhen Hu (2022). Capillary Limit of a Sodium Screen-Wick Heat Pipe. SSRN Electronic Journal.DOI
Lanfei Yuan, Chenglong Wang, Zhipeng Liu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). Numerical Study on Thermal-Hydraulic Characteristics of Lead-Bismuth Loop System Under Moving Conditions. SSRN Electronic Journal.DOI
Xinyu Li, Dalin Zhang, Xindi Lv, Xingguang Zhou, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). Design and Optimization of the Heat Transport and Passive Residual Heat Removal System for Fluoride-Salt-Cooled High-Temperature Advanced Reactor (FuSTAR). SSRN Electronic Journal.DOI
Yu Liang, Dalin Zhang, Jing Zhang, Xiao Liu, Yapeng Liu, Lei Zhou, Yutong Chen, Konstantin Mikityuk, Xiaoyu Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). A Subchannel Analysis Code Star for Sodium-Cooled Fast Reactor. SSRN Electronic Journal.DOI
Hai Wang Yang, Chenglong Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). Experimental Study on Thermoelectric Characteristics of Heat Pipe Reactor (Nuster-100) Single Assembly. SSRN Electronic Journal.DOI
Yin Zhang, Jingyu NIE, Chenglong Wang, Kailun Guo, Wenxi Tian, Guanghui Su, Suizheng Qiu (2022). Neutronic/Thermal-Hydraulic Coupling Analysis of Heat Pipe Reactor Nuster-100 Based on Comsol. SSRN Electronic Journal.DOI
Zhipeng Liu, Yafeng Zhao, Wenxi Tian, Chenglong Wang, Suizheng Qiu, Guanghui Su (2022). Flow Fluctuations and Flow Friction Characteristics of Lead-Bismuth Eutectic in a Vertical Tube Under Rolling Conditions. SSRN Electronic Journal.DOI
Yixin Zhang, Jiaxin Zhang, Chenglong Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). Validation of Lead-Bismuth Thermal Hydraulic Facilities Based on Modified Relap5. SSRN Electronic Journal.DOI
Yandong Hou, Liu Wang, Kui Zhang, Mingjun Wang, Yingwei Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). Experimental Study on Boiling Two-Phase of Liquid Sodium Along a 7-Rod Bundle – Part I:Pressure Drop Characteristics. SSRN Electronic Journal.DOI
Yanan He, Yingwei Wu, Bowen Qiu, Zhao Lei, Liang He, Yongjun Jiao, Ping Chen, Wenxi Tian, Guanghui Su (2022). Development of the Expanding Mandrel Test Facility for Investigation of Zircaloy Cladding Performance Under Loading Strain Rate Similar to Power Ramp. SSRN Electronic Journal.DOI
Xinyu Li, Dalin Zhang, Shichang YUN, Xingguang Zhou, Dianqiang Jiang, Xindi Lv, Zhenyu Feng, Wenqiang Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su, Quanbin Zhao, Xiuting LIU (2022). Design and Optimal Thermal Efficiency Analysis on Closed Brayton Cycle System of Fluoride-Salt-Cooled High-Temperature Advanced Reactor (Fustar). SSRN Electronic Journal.DOI
书籍章节
Jianghan Fu, Jin Hao Zhao, Chenglong Wang, Zhiwen Dai, Wenxi Tian, Guanghui Su, Suizheng Qiu (2023). High-Fidelity Drum Controller Design of Thermionic Space Nuclear Reactor. Springer proceedings in physics.DOI