Hongkang Tian, Tenglong Cong, Junjie Yuan, Xiaowen Wang, Mengjie Li, Qian-Zuo Li, Hanyang Gu (2026). A study of fouling and heat transfer under flow boiling conditions based on a mechanistic bubble dynamics model. Applied Thermal Engineering.DOI
Amjid Rashid, Tenglong Cong, Hanyang Gu (2026). A sensitivity analysis and computational assessment of topology optimization heat sink channel using a power law model. International journal of thermal sciences.DOI
Amjid Rashid, Tenglong Cong, Hanyang Gu (2026). Thermo-hydraulic performance of a topology-optimized straight-channel cold plate using a power law fluid model. International journal of thermal sciences.DOI
Hongkang Tian, Tenglong Cong, Mengjie Li, Xiaowen Wang, Hanyang Gu (2026). Experimental investigation of the deposition behavior of Fe3O4 particles under subcooled nucleate boiling conditions. Corrosion Science.DOI
Tenglong Cong, Jiaqi Gong, Hanyang Gu (2026). Numerical study on the effects of simple spacer grid on critical heat flux. Progress in nuclear energy (New series).DOI
C. Zeng, Maolong Liu, Kang Chen, Koji Okamoto, Hanyang Gu (2026). Transient analysis of the safety characteristics on the lead-bismuth eutectic cooled fast reactor LFR-180. Progress in nuclear energy (New series).DOI
Chunxi Wu, Maolong Liu, Tenglong Cong, Hanyang Gu (2026). Development of LWR core severe accident analysis code SATHA: basic models and preliminary validation against ISP-45. Annals of Nuclear Energy.DOI
Junjie Yuan, Bing-Bin Ying, Zheng Jia, Li Liu, Ruiqi Bao, Hanyang Gu (2026). Study on phase evolution modes and transient mass flow rate characteristics during SCO2 pipeline leakage. Energy.DOI
Zi'ang Li, Yuan Lanfei, Chenglong Wang, Dalin Zhang, Pengrui Qiao, Suizheng Qiu, Hanyang Gu (2026). Experimental and numerical investigation of LBE flow and heat transfer in a grid-spaced hexagonal 7-rod bundle with cosine axial power distribution. Progress in Nuclear Energy.DOI
Hao Tang, Shunhang Yang, Shuo Li, Yiwei Wu, Qufei Song, Kunfeng Ma, Hui Guo, Jianhui Wu, Hanyang Gu (2026). Development of depletion calculation method considering continuous reprocessing and fuel flowing for molten salt reactors analysis. Annals of Nuclear Energy.DOI
Jianfeng Xu, Qufei Song, Jiaqi Gong, Hui Guo, Hanyang Gu (2026). Development of a neutronics–thermal–fluid–structure coupling methodology for performance analysis of U-50Zr helical cruciform fuel. Annals of Nuclear Energy.DOI
Junsen Fu, Yao Xiao, Shuo Chen, Wei Zhang, Xinli Gao, Tenglong Cong, Guo Hn, Hanyang Gu (2026). Experimental investigation of boiling crisis in advanced helical fuel assemblies for small nuclear reactors at high pressures. Applied Thermal Engineering.DOI
Kunfeng Ma, Hui Guo, Hanyang Gu, Li Dongyuan, Guohua Chen (2026). Neutronics analysis and design of mechanical shim control strategy for a pressurized water reactors under base load operation. Nuclear Engineering and Design.DOI
Junsen Fu, Junlong Li, Lerui Zhang, Yao Xiao, Hanyang Gu (2026). Experimental investigation on the heat transfer characteristics in a vertical upward wire-wrapped tight lattice bundle with buoyancy effects. Annals of Nuclear Energy.DOI
Hui Guo, Yiwei Wu, Qufei Song, Kunfeng Ma, Limin Liu, Yao Xiao, Hanyang Gu (2026). Neutronics modeling method of core deformation in a small fast reactor using the three-dimensional method of characteristics. Annals of Nuclear Energy.DOI
Hui Guo, Yiwei Wu, Yuyang Shen, Liming Liu, Hanyang Gu (2026). Corrected P1-consistent scattering cross-section generation method using Monte-Carlo for fast reactor neutron transport core calculation. Progress in Nuclear Energy.DOI
Ziyin Liu, Limin Liu, Ziang Guo, Kuaiyuan Feng, Hui Guo, Hanyang Gu (2026). System design and hierarchical mode switching energy management strategy development for a heat pipe-cooled reactor-battery hybrid energy system. Energy.DOI
Guanqun Ding, Jie Sun, Wei Zhang, Xu Yan, Shuo Wang, Jiaming Shang, Junsen Fu, Yao Xiao, Hanyang Gu (2026). Physics-informed coarse-mesh method for thermohydraulic analysis: Two-phase model extension and validation against flow boiling in tubes and rod bundles with mixing vane spacers. Energy.DOI
Guitao Yang, Junsen Fu, Xu Yan, Jing Wang, Limin Liu, Yao Xiao, Hanyang Gu (2026). Experimental investigation of the effects of inclination on gas-liquid two-phase flow characteristics and flow-pattern transition in helical coils via wire-mesh sensors. International Journal of Multiphase Flow.DOI
Ruixiang Wang, Hui Min Guo, Qufei Song, Kunfeng Ma, Yao Xiao, Hanyang Gu (2026). Optimization Design of Boron-Free Small Pressurized Water Reactor with Helical-Cruciform Metallic Fuel Considering the Influence of Control Rod Compensation Operation History. Springer proceedings in physics.DOI
Guitao Yang, Wei Zhang, Bo Yuan, Junsen Fu, Yao Xiao, Hanyang Gu (2026). Prediction Technique for Heat Transfer in Helically Coiled Tubes via Artificial Neural Networks. Springer proceedings in physics.DOI
Ziyin Liu, Limin Liu, Ziang Guo, Kuaiyuan Feng, Hui Min Guo, Hanyang Gu (2026). Hierarchical Energy Management Strategy of the Heat Pipe Cooled reactor—Battery Hybrid Energy System for Ships. Springer proceedings in physics.DOI
Kunpeng Shao, Ziang Guo, Changhe Liu, Ziyin Liu, Limin Liu, Hanyang Gu (2026). Validation of a Transient Analysis Program for Heat Pipe Cooled Reactors Based on KRUSTY Experiments. Springer proceedings in physics.DOI
Ziang Guo, Limin Liu, Ziyin Liu, Yihu Wang, Zhengyu Du, Xiaoqiang He, Hanyang Gu (2026). Numerical Simulation on the Startup of a Non-nuclear Prototype for a Heat Pipe Cooled Space Reactor. Springer proceedings in physics.DOI
Kunfeng Ma, Shengtao Han, R. S. Wang, Qufei Song, Guo Hn, Hanyang Gu (2026). Conceptual Design of a Low Excess Reactivity Heat Pipe Cooled Reactor Core. Springer proceedings in physics.DOI
Yao Xiao, Hengwei Zhang, Xu Yan, Hanyang Gu (2025). Two-group bubble size distribution evolution in vertical two-phase flow: Mechanistic model development and evaluation in a tight-lattice rod bundle. National Science Open.DOI
Ziang Guo, Li-Min Liu, Yihu Wang, Ziyin Liu, Tenglong Cong, Zheng-Yu Du, Xiaoqiang He, Hanyang Gu (2025). Experimental and numerical analysis of a non-nuclear heat pipe space reactor prototype. Applied Thermal Engineering.DOI
Li-Min Liu, Jia-Ming Zhang, Ziyin Liu, Ziang Guo, Maolong Liu, Yao Xiao, Hanyang Gu (2025). Numerical safety analysis on a conceptual design of fluoride-salt-cooled high-temperature reactors under the influence of ocean conditions. Progress in nuclear energy (New series).DOI
Li-Min Liu, Ziang Guo, Ziyin Liu, Yihu Wang, Tenglong Cong, Hanyang Gu (2025). Code development and initial safety analysis of a mega-power heat pipe-cooled reactor coupling with the Brayton energy conversion system. Applied Thermal Engineering.DOI
Yihu Wang, Ziang Guo, Tenglong Cong, Li-Min Liu, Hanyang Gu (2025). Investigation on coupling methods for heat transfer field between a reactor core and heat pipes. Annals of Nuclear Energy.DOI
Jia-Ming Zhang, Li-Min Liu, Ziyin Liu, Tenglong Cong, Hanyang Gu (2025). Numerical simulation of the fluoride salt flow and heat transfer in the pebble bed under pulsating flow conditions. Applied Thermal Engineering.DOI
Li-Min Liu, Ziang Guo, Zheng-Yu Du, Xiaoqiang He, Hanyang Gu (2025). Experimental research on the coupling heat transfer characteristics of the system components of the space heat pipe cooled reactor under the power variation conditions. Applied Thermal Engineering.DOI
Li-Min Liu, Zheng-Yu Du, Ziang Guo, Ziyin Liu, Xiaoqiang He, Hanyang Gu (2025). Experimental research on the startup and shutdown heat transfer behavior of the coupling system of multi-stage heat pipes and radiators. Annals of Nuclear Energy.DOI
Li Liu, Yamin Li, Hanyang Gu (2025). Numerical study on flow field and separation performance of swirl-vane separator under rolling motion conditions. Annals of Nuclear Energy.DOI
Junjie Yuan, Li Liu, Ruiqi Bao, Haotian Luo, Zheng Jia, Shuo Chen, Hanyang Gu (2025). Numerical study of transient jet phenomena and system effects during the SGTR accident in lead-bismuth fast reactor. International journal of thermal sciences.DOI
Li Liu, Zheng Jia, Junjie Yuan, Ruiqi Bao, Haotian Luo, Hanyang Gu, Pengcheng Zhao (2025). A study of corrosion products deposition behavior in a lead-bismuth-cooled wire-wrapped rod bundle based on flow-thermophysical field parameters. Energy.DOI
Junjie Yuan, Li Liu, Ruiqi Bao, Haotian Luo, Zheng Jia, Shuo Chen, Hanyang Gu (2025). Numerical study on fluid-structure interaction of high-pressure CO2 jet impinging on an adjacent tube. International Communications in Heat and Mass Transfer.DOI
Junjie Yuan, Shuai Liu, Li Liu, Ruiqi Bao, Shuo Chen, Hanyang Gu (2025). Wire-mesh sensor technique for void fraction measurement in gas–liquid two-phase flow under varying conductivity conditions. Measurement.DOI
Junjie Yuan, Li Liu, Ruiqi Bao, Haotian Luo, Zheng Jia, Shuo Chen, Hanyang Gu (2025). Numerical study of enhanced boiling phenomena on vertically oriented surfaces with heterogeneous wettability: lattice Boltzmann method. International Journal of Multiphase Flow.DOI
Ruiqi Bao, Li Liu, Junjie Yuan, Hanyang Gu (2025). Steam expansion and pressure fluctuation model based on steam generator tube rupture accident of lead-cooled faster reactor. The Physics of Fluids.DOI
Chunxi Wu, Li Liu, Haotian Luo, Ruiqi Bao, Junjie Yuan, Maolong Liu, Hanyang Gu (2025). Effect of bubble entrainment on thermal–hydraulic performance of LBE-cooled wire-wrapped rod bundles. Annals of Nuclear Energy.DOI
Ruiqi Bao, Li Liu, Junjie Yuan, Hanyang Gu, Pengcheng Zhao (2025). Instability model of water–steam–liquid metal three-phase jet flow during steam generator tube rupture accident in a fast reactor. The Physics of Fluids.DOI
Li Liu, Zheng Jia, Ruiqi Bao, Haotian Luo, Junjie Yuan, Hanyang Gu, Pengcheng Zhao (2025). Deposition model of corrosion particles with multi-mechanism coupling in flowing LBE. Annals of Nuclear Energy.DOI
Junjie Yuan, Li Liu, Ruiqi Bao, Haotian Luo, Zheng Jia, Shuo Chen, Hanyang Gu (2025). Numerical simulation of energy-mass transport in high-pressure liquid CO2 injected into high-temperature liquid lead–bismuth eutectic pool. Applied Thermal Engineering.DOI
Haotian Luo, Li Liu, Junjie Yuan, Ruiqi Bao, Da Li, Xiao-Yan Tian, Hanyang Gu (2025). Numerical simulation of bubble migration characteristics and distribution probability under lead-cooled fast reactor during SGTR accident. Annals of Nuclear Energy.DOI
Changhe Liu, Ziang Guo, Liu Ziyin, Fengjun Zhong, Limin Liu, Hanyang Gu (2025). Prediction of Frozen Startup Temperature in High-Temperature Alkali Metal Heat Pipes Based on Feedforward Neural Network. Springer proceedings in physics.DOI
Qufei Song, Ruixiang Wang, Yuyang Shen, Yiwei Wu, Kuaiyuan Feng, Hui Guo, Yao Xiao, Hanyang Gu (2025). GPU-accelerated few-group 3D Method of Characteristics for full-core neutron transport in Small Modular Reactors. Progress in Nuclear Energy.DOI
Xiaowen Wang, Maolong Liu, Junlong Li, Junsen Fu, Xu Yan, Hongkang Tian, Tenlong Cong, Yao Xiao, Hanyang Gu (2025). Impact of deposition morphology on critical heat flux during pool boiling from horizontal tubes. Annals of Nuclear Energy.DOI
Qufei Song, Junsen Fu, Ruixiang Wang, Yiwei Wu, Hui Guo, Yao Xiao, Hanyang Gu (2025). Neutronics/Thermal-hydraulic coupling analysis of helical cruciform fuel assembly based on 3D method of characteristics and refined subchannel method. Annals of Nuclear Energy.DOI
Yiwei Wu, Qufei Song, Yuyang Shen, Hui Guo, Yao Xiao, Hanyang Gu (2025). Development of a MC/MOC two-step method for sodium fast reactor analysis with transport-corrected flux-moment multigroup cross-section generation method. Annals of Nuclear Energy.DOI
Wei Zhang, Junsen Fu, Shuo Chen, Lijun Yu, Yao Xiao, Hanyang Gu (2025). Investigation of a hybrid neural network framework for CHF prediction in a wire-wrapped rod bundle. Annals of Nuclear Energy.DOI
Limin Liu, Jiaming Zhang, Tenglong Cong, Yao Xiao, Hanyang Gu (2025). Numerical research of flow and heat transfer characteristics of high-Prandtl-number fluoride salt in the pebble bed channel. Progress in Nuclear Energy.DOI
Xiaoxiao Mao, Xingdi Chen, Xiaobin Jian, Yan Qing Feng, Tenglong Cong, Yao Xiao, Hui Min Guo, Hanyang Gu, Shurong Ding (2025). Modeling of the multi-scale related thermo-mechanical coupling behaviors in a helical cruciform fuel assembly. Nuclear Engineering and Design.DOI
Xu Yan, Hengwei Zhang, Yao Xiao, Hanyang Gu (2025). Modeling and prediction of interfacial area transport in two-phase flow within a tight lattice bundle. Annals of Nuclear Energy.DOI
Xin Jin, Lipeng Wang, Hui Guo, Lixin Chen, Xinbiao Jiang, Hanyang Gu (2025). Design and analysis of self-actuated shutdown system in a small lead–bismuth cooled fast reactor. Nuclear Engineering and Design.DOI
Zijian Huang, Hongkang Tian, Mengke Cai, Tenglong Cong, Yao Xiao, Hanyang Gu (2025). Numerical study of boiling crisis characteristics in helical cruciform fuel with axially non-uniform power distribution. Annals of Nuclear Energy.DOI
Qi Zhang, Yi Lin Zhou, Junsen Fu, Hanyang Gu, Tenglong Cong (2025). A numerical study on single-phase heat transfer characteristics of the helical cruciform fuel assembly. Progress in Nuclear Energy.DOI
Shuo Chen, Wei Zhang, Junsen Fu, Chenwei Liu, Yao Xiao, Hanyang Gu (2025). Investigation on effect of mixing factor on developing CHF correlation for fuel assembly. Progress in Nuclear Energy.DOI
Xiaowen Wang, Maolong Liu, Rui Zhang, Tenglong Cong, Yao Xiao, Hanyang Gu (2025). Development of a new onset of film boiling model within the fouling layer. Annals of Nuclear Energy.DOI
Yuyang Shen, Yiwei Wu, Qufei Song, Kuaiyuan Feng, Hui Guo, Hanyang Gu (2025). Transport-corrected flux-moment homogenization method for generating P0 multigroup cross-section based on continuous energy Monte-Carlo. Annals of Nuclear Energy.DOI
Shuo Chen, Tenglong Cong, Yao Xiao, Hanyang Gu, Peixing Xu (2025). Study on dryout characteristics in a 3-rod tight-lattice bundle. Progress in Nuclear Energy.DOI
Kuaiyuan Feng, Qufei Song, Yihu Wang, Hui Guo, Tenglong Cong, Yao Xiao, Hanyang Gu (2025). Development of a MOC-based multiphysics coupling method for analysis of FCM-fueled micro gas-cooled reactor. Nuclear Engineering and Technology.DOI
Guanqun Ding, Yao Xiao, Hanyang Gu (2025). Development of a physics-informed coarse-mesh method and applications to the thermohydraulic analysis of rod bundles with mixing vane spacers. Applied Energy.DOI
Shuo Chen, Junsen Fu, Qi Gao, Yubo Sun, Yao Xiao, Tenglong Cong, Hanyang Gu (2025). Subchannel analysis of post-dryout flow and heat transfer in a tight-lattice fuel assembly. Annals of Nuclear Energy.DOI
Maolong Liu, Ziyi Xu, Cong Shen, Hanyang Gu (2025). Development of a new onset of nucleate boiling model for helical tubes. International Communications in Heat and Mass Transfer.DOI
Xiaowen Wang, Maolong Liu, Junsen Fu, Xu Yan, Hongkang Tian, Tenlong Cong, Yao Xiao, Hanyang Gu (2025). Pool boiling experimental study on the impact of deposition on the nucleate boiling and bubble behavior of horizontally-placed tubes. International Communications in Heat and Mass Transfer.DOI
Qi Zhang, Zhenhai Liu, Yile Zhang, Hua Pang, Mengke Cai, Zhenhan Hong, Guangliang Yang, Haoyu Wang, Li Liu, Yao Xiao, Hanyang Gu (2025). Experimental study and sub-channel analysis on the transverse mixing of the helical cruciform fuel assembly. Nuclear Engineering and Technology.DOI
Jie Sun, Bo Yuan, Guanqun Ding, Junsen Fu, Zhenqin Xiong, Yao Xiao, Hanyang Gu (2025). Investigation of buoyancy and spacer effects on heat transfer in low-flow-rate upward flow of Lead-bismuth alloy. International Communications in Heat and Mass Transfer.DOI
Shuo Chen, Chen Zeng, Yao Xiao, Hanyang Gu (2025). Experimental study of spacer effects on post-dryout heat transfer in a tight-lattice rod bundle. Progress in Nuclear Energy.DOI
Junsen Fu, Yao Xiao, Ziming Wang, Zhengyang Cao, Hanyang Gu (2025). Visualization experimental investigation on flow boiling and critical heat flux characteristics of helical fuel. Annals of Nuclear Energy.DOI
Junlong Li, Yao Xiao, Dahuan Zhu, Qi Zhang, Yan Ling Xu, Junsen Fu, Xiaoyu Wang, Lerui Zhang, Hanyang Gu (2025). Experimental and numerical investigation on the circumferential non-uniform heat transfer characteristics in a wire-wrapped tight lattice bundle. International Communications in Heat and Mass Transfer.DOI
Junsen Fu, Junlong Li, Xiaowen Wang, Qi Zhang, Yao Xiao, Hanyang Gu (2025). Development of a general circumferentially nonuniform heat transfer fuel rod model for subchannel analysis and application to helical fuel rods. Science China Technological Sciences.DOI
Qufei Song, Ruixiang Wang, Hui Guo, Hanyang Gu (2025). MC/MOC two-step method for reactor physics analysis of helical cruciform fuel reactor. Progress in Nuclear Energy.DOI
Tenglong Cong, Yu-Jie Liu, Maolong Liu, Yao Xiao, Hanyang Gu (2024). Corrosion products deposition and its effects on conjugate heat transfer for helical cruciform fuel assembly. Progress in nuclear energy (New series).DOI
Maolong Liu, Cong Shen, Ziyi Xu, C. Zeng, Xiaowen Wang, Li-Min Liu, Hanyang Gu (2024). Numerical study on flow instability of parallel helical tubes under convective heating condition. Annals of Nuclear Energy.DOI
Jiarong Zhang, Li Liu, Shuai Liu, Hanyang Gu (2024). A method for predicting the breakup of gas column in a decaying swirling liquid field. Annals of Nuclear Energy.DOI
Jiarong Zhang, Li Liu, Junjie Yuan, Haotian Luo, Shuai Liu, Hanyang Gu (2024). A study on bubble entrainment rate in a decaying swirling flow field based on the wire-mesh sensor. Annals of Nuclear Energy.DOI
Fan Peng, D. Lu, Rongkun Hong, Hanyang Gu, Chunping Wang, Qianhua Su, Hua Wei (2024). Experimental study on the influence of velocity on hydraulic characteristics in reactor lower plenum. Annals of Nuclear Energy.DOI
Xiaowen Wang, Rui Zhang, Maolong Liu, Tenglong Cong, Li-Min Liu, Li Liu, Hanyang Gu (2024). Development of a heat transfer model for the film boiling regime in a fouling layer. Annals of Nuclear Energy.DOI
Jiarong Zhang, Li Liu, Shuai Liu, Hanyang Gu (2024). A theoretical model of gas column breakup under a swirling flow field based on the jet theory. Annals of Nuclear Energy.DOI
Li-Min Liu, Da-Huan Zhu, Maolong Liu, Deng Li, Jun-Sen Fu, Hui Guo, Yao Xiao, Hanyang Gu (2024). Transient analysis of the safety characteristics on a super carbon-dioxide cooled micro modular reactor. Nuclear Engineering and Design.DOI
Cong Shen, Maolong Liu, Li-Min Liu, Ziyi Xu, C. Zeng, Li Liu, Hanyang Gu (2024). Development of friction factor and heat transfer correlation of liquid metal flow in helical tube bundles. Annals of Nuclear Energy.DOI
Ziyin Liu, Li-Min Liu, Ziang Guo, Hui Guo, Tenglong Cong, Maolong Liu, Hanyang Gu (2024). Numerical simulation of the ocean conditions impact on heat pipe-cooled molten salt reactor core thermal-hydraulic performance. Nuclear Engineering and Design.DOI
Xiaowen Wang, Maolong Liu, Xu Yan, Tenglong Cong, Hanyang Gu (2024). Development of Nusselt number and friction factor models for rough rod bundles based on wall functions. Annals of Nuclear Energy.DOI
Li Liu, Haotian Luo, Junjie Yuan, Ruiqi Bao, Da Li, Xiao-Yan Tian, Hanyang Gu (2024). Numerical simulation and model development of drag coefficient of bubbles in gas-liquid metal two-phase flow. International Journal of Multiphase Flow.DOI
Ruiqi Bao, Li Liu, Shuai Liu, Maolong Liu, Ke Wang, Hanyang Gu (2024). Numerical analysis and structural optimization of a DLC coated capacitance wire-mesh sensor for measuring liquid metal-gas two-phase distribution. Annals of Nuclear Energy.DOI
Li-Min Liu, Ziyin Liu, Ziang Guo, Hanyang Gu (2024). Optimal Design of a Coupling System of Heat Pipe Cooled Reactor With Battery Energy Storage System. Volume 4: SMRs, Advanced Reactors, and Fusion.DOI
Ziang Guo, Li-Min Liu, Ziyin Liu, Hanyang Gu (2024). Development and application of a transient analysis code for heat pipe cooled reactor systems. Nuclear Engineering and Design.DOI
C. Zeng, Cong Shen, Maolong Liu, Xiao-Yan Tian, Da Li, Li-Min Liu, Hanyang Gu (2024). Development of a solidification blockage discriminant model in filling pipelines. Annals of Nuclear Energy.DOI
Cong Shen, Kun Cheng, Hanqing Li, Maolong Liu, C. Zeng, Li-Min Liu, Hanyang Gu (2024). Numerical study on flow instability in parallel helical tubes under ocean conditions. International Communications in Heat and Mass Transfer.DOI
Junjie Yuan, Li Liu, Ruiqi Bao, Da Li, Xiao-Yan Tian, Haotian Luo, Zheng Jia, Maolong Liu, Hanyang Gu (2024). Numerical simulation of jet boiling characteristics of high-pressure water injected into high-temperature liquid lead–bismuth in a confined space. Applied Thermal Engineering.DOI
Xin Jin, Yu-Bo Sun, Hui Guo, Lixin Chen, Xin-Biao Jiang, Li-Peng Wang, Hanyang Gu (2024). Core design and reactivity control optimization of small lead-cooled reactor LFR-180. Nuclear Engineering and Design.DOI
Li Liu, Junjie Yuan, Ruiqi Bao, Haotian Luo, Zheng Jia, Shuo Chen, Hanyang Gu (2024). Numerical simulation of boiling dynamics in liquid Lead-Bismuth injected with multi-rupture high-pressure water jets. International Communications in Heat and Mass Transfer.DOI
Shuai Liu, Li Liu, Hanyang Gu, Ke Wang (2024). Experimental and theoretical study on liquid film thickness of upward annular flow in helically coiled tubes. International Journal of Multiphase Flow.DOI
Li Liu, Zheng Jia, Junjie Yuan, Ruiqi Bao, Haotian Luo, Hanyang Gu (2024). Assessing the impact of CPs transfer on corrosion behavior in the liquid lead-bismuth eutectic cooled system. Corrosion Science.DOI
Xiaowen Wang, Maolong Liu, Tenlong Cong, Gu Hanyang (2024). Development of an Onset of Nucleate Boiling Model and a Nucleate Boiling Heat Transfer Model Within the Fouling Layer.DOI
Guolong Huang, Junsen Fu, Chenwei Liu, Yao Xiao, Hanyang Gu (2024). Development and validation of a subchannel radiative heat transfer model for fuel bundles. Progress in Nuclear Energy.DOI
Hengwei Zhang, Takashi Hibiki, Yao Xiao, Hanyang Gu (2024). Multi-dimensional characteristics of transitional bubbly flow in a tight lattice subchannel. Applied Thermal Engineering.DOI
Hongkang Tian, Tenglong Cong, Maolong Liu, Mengke Cai, Zijian Huang, Hanyang Gu (2024). Numerical simulation of impurity particles migration and deposition within the 5 × 5 fuel assembly under nucleate boiling conditions. Annals of Nuclear Energy.DOI
Zijian Huang, Hongkang Tian, Mengke Cai, Tenglong Cong, Yao Xiao, Hanyang Gu (2024). Numerical investigation on boiling crisis characteristic of a 7-rod HCF assembly in hexagonal lattice. Progress in Nuclear Energy.DOI
Yiwei Wu, Yuyang Shen, Xin Jin, Qufei Song, Yao Xiao, Hui Guo, Hanyang Gu (2024). Development of a design method for burnable poisons in small modular fast reactors. Annals of Nuclear Energy.DOI
Xu Yan, Yao Xiao, Xiaowen Wang, Junlong Li, Hanyang Gu (2024). Two-phase flow evolution and interfacial area transport downstream of the non-mixing vane spacer grid in rod bundle channels. International Communications in Heat and Mass Transfer.DOI
Xu Yan, Yao Xiao, Xiaowen Wang, Junlong Li, Hanyang Gu (2024). Two-phase flow evolution and interfacial area transport downstream of the mixing-vane spacer grid in rod bundle channels. International Journal of Multiphase Flow.DOI
Hengwei Zhang, Takashi Hibiki, Yao Xiao, Hanyang Gu (2024). Two-group drift-flux model in tight lattice subchannel. International Communications in Heat and Mass Transfer.DOI
Kuaiyuan Feng, Qufei Song, Yuyang Shen, Lei Lou, Yao Xiao, Hui Guo, Hanyang Gu (2024). Development and verification of an MC/MOC two-step scheme for neutronic analysis of FCM-fueled micro gas-cooled reactor. Annals of Nuclear Energy.DOI
Hui Guo, Shengtao Han, Xin Jin, Yiwei Wu, Qufei Song, Yao Xiao, Hanyang Gu (2024). Pareto front of sodium void worth and breeding ratio in metal-fueled sodium fast reactor with axially heterogeneous core design by coupling neutronics and genetic algorithm. Nuclear Engineering and Design.DOI
Shuo Chen, Shuai Liu, Li Liu, Li Liu, Yamin Li, Jiarong Zhang, Tenglong Cong, Hanyang Gu (2024). Experimental study on flow patterns and pressure gradient of decaying swirling gas-liquid flow in a horizontal pipe. Progress in Nuclear Energy.DOI
Hengwei Zhang, Takashi Hibiki, Yao Xiao, Hanyang Gu (2024). Some characteristics of air-water two-phase flow in the subchannel of a tight lattice rod bundle. International Communications in Heat and Mass Transfer.DOI
Shuo Chen, Rui Zhang, Maolong Liu, Hui Min Guo, Yao Xiao, Tenglong Cong, Hanyang Gu (2024). Numerical study on the thermohydraulics of near-critical water in rod bundle with spacer grids. Progress in Nuclear Energy.DOI
Junsen Fu, Junlong Li, Lerui Zhang, Qi Zhang, Yao Xiao, Hanyang Gu (2024). General flow sweeping mixing model for subchannel analysis and application to three rod bundles with different typical spacer methods. International Communications in Heat and Mass Transfer.DOI
Qi Zhang, Haoyu Wang, Junlong Li, Quan-yao Ren, Yile Zhang, Yi Lin Zhou, Zengping Pu, Yongzhong Huang, Hanyang Gu (2024). Experimental study on flow resistance and phase distribution of gas-liquid flow in helical cruciform fuel assembly. Annals of Nuclear Energy.DOI
Weidong Zhang, Yao Xiao, Lijun Yu, Hanyang Gu (2024). Prediction of Critical Heat Flux of Wire-Wrapped Rod Bundle Based on Artificial Neural Network.DOI
Qi Zhang, Haoyu Wang, Junlong Li, Chenxi Li, Feipeng Qi, Yi Zhou, Hanyang Gu, Tenglong Cong, Yao Xiao (2024). Numerical simulation of flow and heat transfer phenomenon of helical cruciform fuel assembly under subcooled boiling. Progress in Nuclear Energy.DOI
Yubo Sun, Yao Xiao, Junlong Li, Junsen Fu, Maolong Liu, Hui Nan Guo, Xiaoyan Tian, Xinbiao Jiang, Lixin Chen, Hanyang Gu (2024). Development and application of a refined subchannel analysis code for lead-based wire-wrapped bundles. Annals of Nuclear Energy.DOI
Mengke Cai, Changqiu Ji, Tenglong Cong, Tenglong Cong, Yinan Cui, Yinan Cui, Hanyang Gu (2024). A probabilistic coupled hardening model of double irradiation defects in iron. Journal of Nuclear Materials.DOI
Xiaowen Wang, Maolong Liu, Rui Zhang, Junsen Fu, Tenglong Cong, Hanyang Gu (2024). Investigation on turbulent heat transfer to lead-bismuth eutectic flows in rough rod bundles for nuclear applications. International Journal of Thermal Sciences.DOI
Yihu Wang, Kuaiyuan Feng, Yiwei Wu, Limin Liu, Hui Guo, Tenglong Cong, Hanyang Gu (2024). Numerical study on the neutronics-thermal-mechanics coupling characteristics of the heat pipe nuclear reactor core. Annals of Nuclear Energy.DOI
Limin Liu, Liu Ziyin, Jiaming Zhang, Cong Shen, Maolong Liu, Yao Xiao, Hanyang Gu (2024). Numerical research on the influence of ocean conditions on the transient response of passive decay heat removal system of the floating Fluoride-Salt-Cooled High-Temperature Reactors. Annals of Nuclear Energy.DOI
Limin Liu, Cong Shen, Maolong Liu, Yao Xiao, Tenglong Cong, Hanyang Gu (2024). Numerical simulation of the thermal-hydraulic characteristics of the liquid metal flow across the single-start helical coiled tube bundles. Progress in Nuclear Energy.DOI
Mengke Cai, Tenglong Cong, Yao Xiao, Hanyang Gu (2024). Multi-physics coupling behaviors on 3 × 3 helical cruciform fuel rods of U-50Zr alloy under normal and accident conditions. Annals of Nuclear Energy.DOI
Junsen Fu, Junlong Li, Ziming Wang, Tenglong Cong, Hui Nan Guo, Yao Xiao, Hanyang Gu (2024). Numerical study of the effect of helical fuel rod geometry on single-phase flow and heat transfer characteristics. Annals of Nuclear Energy.DOI
Hengwei Zhang, Yao Xiao, Hanyang Gu (2024). Fully developed pipeline flow fast simulation model and application to a rod bundle subchannel. Annals of Nuclear Energy.DOI
Wei Zhang, Junsen Fu, Jun Cui, Xiangfei Meng, Shuo Chen, Lijun Yu, Yao Xiao, Hanyang Gu (2024). Experimental investigation and prediction of CHF in wire-wrapped rod bundles. Applied Thermal Engineering.DOI
Kuaiyuan Feng, Jipu Hu, Yihu Wang, Tenglong Cong, Hanyang Gu, Hui Guo (2024). Multiphysics analysis of a metal hydride moderated megawatt heat pipe reactor with burnable poisons. Frontiers in Energy Research.DOI
Qufei Song, Chang Zhang, Yiwei Wu, Kuaiyuan Feng, Hui Guo, Hanyang Gu (2024). Time-dependent neutron transport method based on three-dimensional method of characteristics. Annals of Nuclear Energy.DOI
Hui Guo, Yuyang Shen, Yiwei Wu, Qufei Song, Hanyang Gu (2024). Generating multi-group cross-sections using continuous-energy Monte Carlo method for fast reactor analysis. EPJ Web of Conferences.DOI
Yi-Wei Wu, Qu-Fei Song, Hao Xu, Jipu Hu, Hanyang Gu, Hui Guo (2023). GENERATION OF MULTI-GROUP CROSS-SECTIONS FOR MICROREACTOR WITH WHOLE-CORE SUPERHOMOGENIZATION EQUIVALENCE TECHNIQUE. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Qu-Fei Song, Chang Zhang, Chun-Tao Tang, Yi-Wei Wu, Hanyang Gu, Hui Guo (2023). MULTI-OBJECTIVE OPTIMIZATION OF MOC PARAMETERS BASED ON GENETIC ALGORITHM. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Cong Shen, Maolong Liu, Zihan Xu, Kun Cheng, Li-Min Liu, Hanyang Gu (2023). Study on two-phase flow instability of parallel helical tubes in steam generator of small modular reactors. International Communications in Heat and Mass Transfer.DOI
C. Zeng, Hao Lin, Weihao Zhang, Qi Zhang, Li-Min Liu, Li Liu, Maolong Liu, Hanyang Gu (2023). STUDY ON FREEZING TOLERANCE DESIGN OF THE DIRECT REACTOR AUXILIARY COOLING SYSTEM (DRACS) FOR FLUORIDE-SALT-COOLED HIGH-TEMPERATURE REACTOR (FHR). The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Ziyin Liu, Li-Min Liu, Hao Xu, Maolong Liu, Hui Guo, Hanyang Gu, Tenglong Cong (2023). THERMAL-HYDRAULIC ANALYSIS ON A HEAT PIPE COOLED MOLTEN SALT REACTOR UNDER THE INFLUENCE OF THE MARINE CONDITIONS. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Yu-Bo Sun, Yao Xiao, Jun-Long Li, Xin-Biao Jiang, Lixin Chen, Hanyang Gu (2023). DEVELOPMENT OF A REFINED SUB-CHANNEL ANALYSIS CODE FOR LEAD-BASED COOLED FAST REACTOR. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Hengwei Zhang, Yao Xiao, Xu Yan, Hanyang Gu (2023). A two-dimensional void fraction distribution fast prediction model and application to a rod bundle. International Communications in Heat and Mass Transfer.DOI
Hui Guo, Yiwei Wu, Qufei Song, Yuyang Shen, Hanyang Gu (2023). Development of multi-group Monte-Carlo transport and depletion coupling calculation method and verification with metal-fueled fast reactor. Nuclear Science and Techniques.DOI
Mengke Cai, Tenglong Cong, Hanyang Gu (2023). Multiphysics fuel performance modeling of dispersed TRISO-coated particle fuel plate under long-time normal condition and accident conditions. Nuclear Engineering and Design.DOI
Zhang Chang, Qufei Song, Hui Guo, Tenglong Cong, Yao Xiao, Hanyang Gu (2023). Reactivity control optimization of boron-free small modular pressurized water reactor with helical-cruciform metallic fuel. Nuclear Engineering and Design.DOI
Xu Yan, Yao Xiao, Hengwei Zhang, Hanyang Gu (2023). Experimental investigation of gas-phase migration behaviors in a tight lattice bundle under two-phase non-equilibrium flow. Chemical Engineering Science.DOI
Qufei Song, Chang Zhang, Yiwei Wu, Kuaiyuan Feng, Hui Guo, Hanyang Gu (2023). Multi-objective optimization of method of characteristics parameters based on genetic algorithm. Annals of Nuclear Energy.DOI
Xu Yan, Yao Xiao, Hengwei Zhang, Hanyang Gu (2023). Study of gas-liquid two-phase flow redistribution characteristics in the rod bundle channel using wire-mesh sensor. Chemical Engineering Science.DOI
Chen Zeng, Maolong Liu, Weihao Zhang, Limin Liu, Li Liu, Hanyang Gu (2023). Development and validation of a one-dimensional solidification model — Part II: Model validation for molten lead-bismuth. Annals of Nuclear Energy.DOI
Chen Zeng, Maolong Liu, Weihao Zhang, Limin Liu, Li Liu, Hanyang Gu (2023). Development and validation of a one-dimensional solidification model — Part I: Analytical model. Annals of Nuclear Energy.DOI
Tenglong Cong, Hao Chen, Hanyang Gu (2023). Upgradation of fission gas release model in the nuclear fuel analysis code FuSPAC. Progress in Nuclear Energy.DOI
Xin Jin, Zimu Zhang, Yubo Sun, Maolong Liu, Yao Xiao, Hui Guo, Xinbiao Jiang, Lixin Chen, Hanyang Gu (2023). Preliminary safety comparison of lead-cooled fast reactors with advanced fuels in unprotected transients. Nuclear Engineering and Design.DOI
Mengke Cai, Tenglong Cong, Hongkang Tian, Hanyang Gu (2023). Porosity effect on the thermal and mechanical properties of U-50Zr alloy: A molecular dynamics study. Journal of Nuclear Materials.DOI
Xu Yan, Yao Xiao, Hengwei Zhang, Hanyang Gu (2023). Periodic large-scale structural characteristics of two-phase flow in tight lattice bundles. International Journal of Heat and Mass Transfer.DOI
Junlong Li, Yao Xiao, Junsen Fu, Qi Zhang, Zhenqin Xiong, Hanyang Gu (2023). Experimental analysis and two-region mixing coefficients development for a wire-wrapped tight lattice bundle. Annals of Nuclear Energy.DOI
Mengke Cai, Tenglong Cong, Yao Xiao, Hanyang Gu (2023). Multi-physical fuel performance modeling of U-50Zr helical cruciform fuel based on fluid-thermal-structure coupling methodology. Annals of Nuclear Energy.DOI
Junjie Yuan, Li Liu, Ruiqi Bao, Haotian Luo, Maolong Liu, Hanyang Gu (2023). Three-dimensional numerical simulation of the interaction between high-pressure sub-cooled water jet impacting high-temperature liquid lead-bismuth metal. Applied Thermal Engineering.DOI
Hui Guo, Yiwei Wu, Qufei Song, Tenglong Cong, Hanyang Gu (2023). Development of OpenMC/Trivac two-step scheme for fast reactor core neutronics analysis. Annals of Nuclear Energy.DOI
Ke Wang, Li Liu, Dehui Xu, Hanyang Gu (2023). Simulation and optimization of a conical type swirl-vane separator in nuclear SG. Nuclear Engineering and Design.DOI
Yiwei Wu, Qufei Song, Kuaiyuan Feng, Jean–François Vidal, Hanyang Gu, Hui Guo (2023). Multigroup cross-sections generated using Monte-Carlo method with flux-moment homogenization technique for fast reactor analysis. Nuclear Engineering and Technology.DOI
Tenglong Cong, Junjie Wang, Hanyang Gu (2023). Numerical study on flow-induced vibration of LBE-cooled wire-wrapped rod bundle. Annals of Nuclear Energy.DOI
Junlong Li, Yao Xiao, Junsen Fu, Zhenqin Xiong, Hanyang Gu (2023). Development of a general flow sweeping mixing model and application to a wire-wrapped assembly. International Communications in Heat and Mass Transfer.DOI
Yiwei Wu, Qufei Song, Ruixiang Wang, Yao Xiao, Hanyang Gu, Hui Guo (2023). Development and verification of a Monte Carlo two-step method for lead-based fast reactor neutronics analysis. Nuclear Engineering and Technology.DOI
Junsen Fu, Yao Xiao, Junlong Li, Qi Zhang, Tenglong Cong, Hanyang Gu (2023). Development of a refined helical fuel mixing model and application to a helical fuel rod bundle. Science China Technological Sciences.DOI
Guanqun Ding, Nan Li, Бо Лю, Junlong Li, Yao Xiao, Hanyang Gu (2023). Numerical study of mixed and free convection heat transfer under ocean conditions. International Journal of Heat and Mass Transfer.DOI
Shuai Liu, Ke Wang, Li Liu, Qi Zhang, Hanyang Gu (2022). Characterization of liquid film distribution and sub-flow regimes of annular flow in helically coiled tubes using ring island array sensor. International Journal of Multiphase Flow.DOI
Maolong Liu, Yiwei Wei, Lang Wang, Zhenqin Xiong, Hanyang Gu (2022). An accident diagnosis method of pressurized water reactor based on BI-LSTM neural network. Progress in Nuclear Energy.DOI
Hengwei Zhang, Yao Xiao, Xu Yan, Hanyang Gu (2022). Experimental investigation on interfacial parameters of two-phase flow in a tight lattice rod bundle with optimized data processing method. International Communications in Heat and Mass Transfer.DOI
Mengke Cai, Tenglong Cong, Yao Xiao, Hanyang Gu (2022). Preliminary Thermal-Mechanical coupled modeling of U-10Mo helical cruciform fuel rods under the unirradiated and irradiated conditions. Annals of Nuclear Energy.DOI
Wei Zhang, Yao Xiao, Ya Nan Ye, Chen Hu, Zhen Jia, Cong Wang, Lijun Yu, Hanyang Gu (2022). Experimental investigation of side-discharge sparger on pressure oscillation in steam jet condensation. Applied Thermal Engineering.DOI
Hui Guo, Yiwei Wu, Xin Jin, Kuaiyuan Feng, Xingkai Huo, Hanyang Gu (2022). Preliminary verification of multi-group cross-sections generation and locally heterogeneous transport calculation using OpenMC with CEFR start-up tests benchmark. Progress in Nuclear Energy.DOI
Xiaowen Wang, Cong Shen, Limin Liu, Maolong Liu, Hanyang Gu (2022). Development of heat transfer correlation of turbulent forced convection in subchannels with rough surfaces based on CFD. Annals of Nuclear Energy.DOI
Junlong Li, Yao Xiao, Tenglong Cong, Zhenqin Xiong, Hanyang Gu (2022). Numerical analysis of the subcooled boiling phenomena in a wire-wrapped annulus. International Journal of Heat and Mass Transfer.DOI
Limin Liu, Dahuan Zhu, Maolong Liu, Dengwei Li, Hui Guo, Yao Xiao, Hanyang Gu (2022). Investigation of the safety limits and the limiting safety system settings on a super carbon-dioxide cooled micro modular reactor. Annals of Nuclear Energy.DOI
Cong Shen, Limin Liu, Ziyi Xu, Hanyang Gu, Maolong Liu (2022). Influence of helix angle on flow and heat transfer characteristics of lead–bismuth flow in helical-coiled tube bundles. Annals of Nuclear Energy.DOI
Tenglong Cong, Qi Zhang, Junzhi Zhu, Yao Xiao, Hui Min Guo, Hanyang Gu (2022). Transverse mixing characteristics of single-phase flow in the helical cruciform fuel assembly. Annals of Nuclear Energy.DOI
Tenglong Cong, Bicheng Wang, Hanyang Gu (2022). Numerical analysis on heat transfer enhancement of sCO2 in the tube with twisted tape. Nuclear Engineering and Design.DOI
Tenglong Cong, Hao Chen, Chao Chen, Shaohong Zhang, Hanyang Gu (2022). Development and evaluation of fuel performance analysis code FuSPAC. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
Chen Zeng, Yinxi Song, Xiang Zhou, Feixi Zhang, Mengke Chao, Ming Jiao, Maolong Liu, Hanyang Gu (2022). Optimization of the thermal-hydraulic performance of zigzag-type microchannel heat exchangers using asymmetric geometry. Applied Thermal Engineering.DOI
Chang Zhang, Ruixiang Wang, Hui Guo, Hanyang Gu, Yao Xiao (2022). Coupled OpenMC/CTF to VERA Core Physics Benchmark Problem 6. Volume 15: Student Paper Competition.DOI
Mengke Cai, Tenglong Cong, Hanyang Gu (2022). Preliminary Prediction of Young’s Modulus and Thermal Conductivity of Porous U-50 wt.% Zr Alloy: A Molecular Dynamic and Semi-Empirical Study. Volume 15: Student Paper Competition.DOI
Cong Shen, Limin Liu, Maolong Liu, Hanyang Gu (2022). Numerical Investigations of the LBE Flow and Heat Transfer Characteristics in the Helical-Coiled Tube Bundle. Volume 15: Student Paper Competition.DOI
Maolong Liu, Ziyi Xu, Yao Xiao, Hanyang Gu (2022). Development of a 1d Code for Heat Transfer Characteristics of Helical-Coiled Once-Through Steam Generators.DOI
Junlong Li, Yao Xiao, Guanqun Ding, Zhenqin Xiong, Hanyang Gu (2022). Numerical analysis of the three-dimensional flow phenomena in a 19-pin wire-wrapped tight lattice bundle. International Journal of Heat and Mass Transfer.DOI
Ziyi Xu, Mengke Chao, Wei Zhang, Feixi Zhang, Yao Xiao, Maolong Liu, Hanyang Gu (2022). Experimental and numerical study of the thermal hydraulics characteristics of a helical-coiled once-through steam generator. Applied Thermal Engineering.DOI
Yao Xiao, Junlong Li, Guanqun Ding, Бо Лю, Hanyang Gu (2022). Numerical study of spacer-induced heat transfer impairment in mixed and free convection heat transfer of water upward flow. International Communications in Heat and Mass Transfer.DOI
Qi Zhang, Tenglong Cong, Yao Xiao, Junlong Li, Chen Zeng, Hanyang Gu (2022). Comparison on the thermal–hydraulic characteristics of wire-wrapped fuel and helical cruciform fuel by numerical simulation. Annals of Nuclear Energy.DOI
Limin Liu, Бо Лю, Yao Xiao, Hanyang Gu, Hui Guo (2022). Preliminary thermal and mechanical analysis on the reactor core of a new heat pipe cooled reactor applied in the underwater environment. Progress in Nuclear Energy.DOI
Li Liu, Bing Hu, Shuai Liu, Ke Wang, Hanyang Gu (2022). Recognition of gas-liquid flow regimes in helically coiled tube using wire-mesh sensor and KNN algorithm. International Journal of Multiphase Flow.DOI
Li Liu, Jiarong Zhang, Bing Hu, Juntao Dai, Ke Wang, Hanyang Gu (2022). Flow pattern transition and void fraction prediction of gas–liquid flow in helically coiled tubes. Chemical Engineering Science.DOI
Hui Guo, Xingkai Huo, Kuaiyuan Feng, Hanyang Gu (2022). Verification of OpenMC for fast reactor physics analysis with China experimental fast reactor start-up tests. Nuclear Engineering and Technology.DOI
Hui Guo, Xin Jin, Xingkai Huo, Hanyang Gu, Haicheng Wu (2022). Influence of nuclear data library on neutronics benchmark of China experimental fast reactor start-up tests. Nuclear Engineering and Technology.DOI
Tenglong Cong, Jiaqi Gong, Yao Xiao, Hanyang Gu (2022). Numerical study on the effects of guide thimble on critical heat flux in a 5 × 5 fuel assembly. Annals of Nuclear Energy.DOI
Maolong Liu, Song Ni, Xiaowen Wang, Limin Liu, Hanyang Gu (2022). Experimental study on the natural circulation behavior of a full-scale PWR fuel assembly. Annals of Nuclear Energy.DOI
Maolong Liu, Song Ni, Xiaowen Wang, Limin Liu, Hanyang Gu (2022). Development of analytical models for the natural circulation behavior of a full-scale PWR fuel assembly. Annals of Nuclear Energy.DOI
Maolong Liu, Xiaowen Wang, Song Ni, Limin Liu, Hanyang Gu (2022). Development of friction factor correlations for hexagonal and square bundles with rough rods based on CFD. Annals of Nuclear Energy.DOI
Shuai Liu, Li Liu, Hanyang Gu, Ke Wang (2022). Optimization and application of the concentric conductance probes in liquid film thickness measurement in a helically coiled tube. Measurement Science and Technology.DOI
Qi Zhang, Li Liu, Yue Zeng, Chen Zeng, Hanyang Gu (2022). Numerical simulation of inherent boric mixing phenomenon inside reactor annular down-comer. Progress in Nuclear Energy.DOI
Hangbin Zhao, Qi Zhang, Hanyang Gu, Yao Xiao, Maolong Liu (2022). CFD investigation on thermal-hydraulic characteristics of a helical cruciform fuel bundle. Progress in Nuclear Energy.DOI
Chen Zeng, Yinxi Song, Xiang Zhou, Feixi Zhang, Ming Jiao, Maolong Liu, Hanyang Gu (2022). Experimental study on heat transfer and pressure drop characteristics in a microchannel heat exchanger assembly with S-shaped fins. Applied Thermal Engineering.DOI
Tenglong Cong, Rui Zhang, Bicheng Wang, Yao Xiao, Hanyang Gu (2022). Single-phase flow in helical cruciform fuel assembly with conjugate heat transfer. Progress in Nuclear Energy.DOI
Shuai Liu, Li Liu, Hanyang Gu, Ke Wang (2022). Experimental study of gas-liquid flow patterns and void fraction in prototype 5 × 5 rod bundle channel using wire-mesh sensor. Annals of Nuclear Energy.DOI
Junlong Li, Chaozhu Zhang, Qi Zhang, Ping Yang, Fujun Gan, Shuo Chen, Zhenqin Xiong, Yao Xiao, Hanyang Gu (2022). Experimental investigation on onset of nucleate boiling and flow boiling heat transfer in a 5 × 5 rod bundle. Applied Thermal Engineering.DOI
Tenglong Cong, Cong Zheng, Rui Zhang, Hanyang Gu (2022). Prediction of thermohydraulics in shell side of CAP1400 steam generator by two-fluid porous media model. Progress in Nuclear Energy.DOI
Hangbin Zhao, Hanyang Gu, Maolong Liu, Yao Xiao (2021). Numerical investigation of transverse flow and turbulent mixing in a helical cruciform fuel bundle. Annals of Nuclear Energy.DOI
Ziyi Xu, Maolong Liu, Cong Chen, Yao Xiao, Hanyang Gu (2021). Development of an analytical model for the dryout characteristic in helically coiled tubes. International Journal of Heat and Mass Transfer.DOI
Tenglong Cong, Yao Xiao, Bicheng Wang, Hanyang Gu (2021). Numerical study on the boiling heat transfer and critical heat flux in a simplified fuel assembly with 2×2 helical cruciform rods. Progress in Nuclear Energy.DOI
Junlong Li, Zhanfei Qi, Kemei Cao, Maolong Liu, Zijiang Yang, Yao Xiao, Zhenqin Xiong, Hanyang Gu (2021). Experimental investigation on the heat removal capacity of secondary side passive residual heat removal system for an integrated reactor. Applied Thermal Engineering.DOI
Kuaiyuan Feng, Yiwei Wu, Jipu Hu, Xin Jin, Hanyang Gu, Hui Guo (2021). Preliminary analysis of a zirconium hydride moderated megawatt heat pipe reactor. Nuclear Engineering and Design.DOI
Chen Zeng, Xiao Gang Chu, Limin Liu, Maolong Liu, Hanyang Gu (2021). Performance evaluation of DRACS system of molten salt reactors using a transient solidification model. Nuclear Engineering and Design.DOI
Botao Zhang, Shengjie Gong, Fujun Gan, Chaozhu Zhang, Hanyang Gu (2021). Flow induced vibration measurement for a 4 × 4 rod bundle with spacer grids by the Laser Doppler Vibrometer. Annals of Nuclear Energy.DOI
Maolong Liu, Lang Wang, Song Ni, Xiaowen Wang, Limin Liu, Hanyang Gu (2021). Experimental investigation on pressure drop of a PWR fuel assembly under low Re conditions. Annals of Nuclear Energy.DOI
Hui Guo, Xingjie Peng, Yiwei Wu, Xin Jin, Kuaiyuan Feng, Hanyang Gu (2021). Neutronics modelling of control rod compensation operation in small modular fast reactor using OpenMC. Nuclear Engineering and Technology.DOI
Maolong Liu, Chen Zeng, Limin Liu, Hanyang Gu (2021). Evaluation of a freeze-tolerant decay heat removal system redundancy for fluoride salt-cooled high-temperature reactors (FHR). Annals of Nuclear Energy.DOI
Qi Zhang, Li Liu, Yao Xiao, Junsen Fu, Hanyang Gu (2021). Experimental study on the transverse mixing of 5 × 5 helical cruciform fuel assembly by wire mesh sensor. Annals of Nuclear Energy.DOI
Hui Guo, Xin Jin, Kuaiyuan Feng, Hanyang Gu (2021). Alternative Absorber Materials for Control Rods in ALFRED.DOI
Hengwei Zhang, Yao Xiao, Hanyang Gu (2021). Interfacial area concentration and bubble size distribution measurement using tomography technique. International Journal of Multiphase Flow.DOI
Yao Xiao, Junsen Fu, Qi Zhang, Hangbin Zhao, Hanyang Gu (2021). Development of a flow sweeping mixing model for helical fuel rod bundles. Annals of Nuclear Energy.DOI
Yao Xiao, Wei Zhang, Junlong Li, Xingli Gao, Chao Huang, Hanyang Gu (2021). Effects of edge geometry on the flow-induced acoustic resonances in closed side branches. Annals of Nuclear Energy.DOI
Hengwei Zhang, Yao Xiao, Hanyang Gu (2021). Experimental investigation of two-phase flow evolution in a tight lattice bundle using wire-mesh sensor. International Journal of Heat and Mass Transfer.DOI
Junlong Li, Yao Xiao, Hanyang Gu, Da Liu, Qi Zhang (2021). Development of a correlation for mixed convection heat transfer in rod bundles. Annals of Nuclear Energy.DOI
Hui Guo, Kuaiyuan Feng, Hanyang Gu, Xue Feng Yao, L. Bo (2021). Neutronic modeling of megawatt-class heat pipe reactors. Annals of Nuclear Energy.DOI
Li Liu, Jiarong Zhang, Shuai Liu, Ke Wang, Hanyang Gu (2021). Decay law and swirl length of swirling gas-liquid flow in a vertical pipe. International Journal of Multiphase Flow.DOI
Qi Zhang, Hanyang Gu, Shuai Liu, Junlong Li, Sichao Tan, Jianke Su (2020). Flow Visualization of Centrifugal Pump by the Combination of LIF and PIV. International Conference on Sensing, Measurement & Data Analytics in the era of Artificial Intelligence (ICSMD).DOI
Shuai Liu, Li Liu, Jiarong Zhang, Hanyang Gu, Qi Zhang (2020). Application of Wire Mesh Sensor to Identify Gas-liquid Flow Patterns in a Horizontal Pipe. International Conference on Sensing, Measurement & Data Analytics in the era of Artificial Intelligence (ICSMD).DOI
Shuai Liu, Li Liu, Jiarong Zhang, Hanyang Gu (2020). Experimental Study on Flow Patterns of Decaying Swirling Gas-Liquid Flow in a Horizontal Pipe.DOI
Hengwei Zhang, Yao Xiao, Hanyang Gu (2020). An Experimental Study of Two-Phase Flow in a Tight Lattice Using Wire-Mesh Sensor.DOI
Jiarong Zhang, Li Liu, Shuai Liu, Hanyang Gu (2020). Experimental Study on Flow Patterns and Pressure Drop of Decaying Swirling Gas-Liquid Flow in a Vertical Pipe.DOI
Jiaqi Tao, Hanyang Gu, Zhenqin Xiong, Xing Jiang, Yongcheng Xie (2020). Numerical and experimental study on thermal-hydraulic behaviors in the secondary side of passive residual heat removal heat exchanger. Annals of Nuclear Energy.DOI
Limin Liu, Jian Deng, Dalin Zhang, Hanyang Gu (2020). Review of the experimental research on the thermal‐hydraulic characteristics in the pebble bed nuclear reactor core and fusion breeder blankets. International Journal of Energy Research.DOI
Li Liu, Bingbin Ying, Hanyang Gu, Dehui Xu, Chao Huang, Shuo Chen (2020). Effect of velocity and pressure on performance of a full-scale SG steam separator package. Nuclear Engineering and Design.DOI
Li Liu, Bingbin Ying, Hanyang Gu, Dehui Xu, Chao Huang, Shuo Chen (2020). Experimental study on the separation performance of a full-scale SG steam-water separator. Annals of Nuclear Energy.DOI
Maolong Liu, Chen Zeng, Zilin Luo, Hanyang Gu, Jian Deng (2020). Optimization of the TRISO fuel particle distribution based on octahedral and icosahedral-based segmentation methods in the pebble-bed nuclear core. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
Ziyi Xu, Maolong Liu, Yao Xiao, Hanyang Gu (2020). Development of a RELAP5 model for the thermo-hydraulic characteristics simulation of the helically coiled tubes. Annals of Nuclear Energy.DOI
Fan Peng, Qianhua Su, Jun Xing, Donghua Lu, Chunyu Wang, Hanyang Gu (2020). Experimental study on flow distribution and mixing at the core inlet of double-loop small module reactor. Annals of Nuclear Energy.DOI
Song Ni, Maolong Liu, Hanyang Gu (2020). Modeling and validation of RELAP5 for natural circulation flow in a single PWR fuel assembly. Annals of Nuclear Energy.DOI
Shuo Chen, Hanyang Gu, Maolong Liu, Yao Xiao, Dawei Cui (2019). Experimental investigation on heat transfer to supercritical water in a three-rod bundle with spacer grids. Applied Thermal Engineering.DOI
Shuo Chen, Da Liu, Maolong Liu, Yao Xiao, Hanyang Gu (2019). Numerical simulation and analysis of flow and heat transfer in a 5 × 5 vertical rod bundle with buoyancy effects. Applied Thermal Engineering.DOI
Shuo Chen, Hanyang Gu (2019). CFD simulation and analysis of reactor integral hydraulic tests. Annals of Nuclear Energy.DOI
Zhengting Quan, Kefeng Zhang, Zhenqin Xiong, Hong-biao Zu, Hanyang Gu, Yongcheng Xie (2019). Experimental study on cross flow induced vibration response of four-span straight tube bundle with TSP or AVB supports. Nuclear Engineering and Design.DOI
Shuo Chen, Da Liu, Yao Xiao, Hanyang Gu (2019). Experimental study on onset of nucleate boiling and flow boiling heat transfer in a 5 × 5 rod bundle at low flow rate. International Journal of Heat and Mass Transfer.DOI
Shuo Chen, Yao Xiao, Hanyang Gu (2019). Experimental study on boiling heat transfer in a three-rod bundle at near-critical pressure. Annals of Nuclear Energy.DOI
Jiaqi Tao, Hanyang Gu, Zhenqin Xiong, Xing Jiang, Yongcheng Xie (2019). Investigation on transient thermal hydraulics of reduced scale passive residual heat removal heat exchanger in tank. Annals of Nuclear Energy.DOI
Minghui Duan, Minfu Zhao, Hanyang Gu (2019). AN EXPERIMENTAL RESEARCH OF THE RESISTANCE CHARACTERISTICS OF THE ANNULAR FUEL ASSEMBLY. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Zhang Qi, Zhao Hangbin, Gu Hanyang, Tan Sichao, Peng Wang, Yang Yunjia (2019). Boron concentration field measurement and mixing analysis in the annular downcomer of reactor pressure vessel. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Jiayue Chen, Hanyang Gu, Zhenqin Xiong (2018). Development of one-dimensional transient model for predicting flow instability at supercritical pressures. Progress in Nuclear Energy.DOI
Minglu Wang, Zheng Mingguang, Rui Wang, Lin Tian, Cheng Ye, Yan Chen, Hanyang Gu (2018). Experimental studies on local and average heat transfer characteristics in helical pipes with single phase flow. Annals of Nuclear Energy.DOI
Yong Mei, Shengjie Gong, Hanyang Gu, Weimin Ma (2018). A study on steam-water two phase flow distribution in a rectangular channel with different channel orientations. Experimental Thermal and Fluid Science.DOI
Jiayue Chen, Hanyang Gu, Zhenqin Xiong (2018). A circumferentially non-uniform heat transfer model for subchannel analysis of tight rod bundles. Annals of Nuclear Energy.DOI
Jiaqi Tao, Hanyang Gu, Zhenqin Xiong, Xing Jiang, Yongcheng Xie (2018). Parametric analysis of heat transfer rate of passive residual heat removal heat exchanger submerged in water tank. Experimental Thermal and Fluid Science.DOI
Zhenxiao Hu, Da Liu, Hanyang Gu (2018). Study on spacer-induced heat transfer deterioration of supercritical water in annular channel. International Journal of Heat and Mass Transfer.DOI
Yong Mei, Yunhao Shao, Shengjie Gong, Yechen Zhu, Hanyang Gu (2018). Effects of surface orientation and heater material on heat transfer coefficient and critical heat flux of nucleate boiling. International Journal of Heat and Mass Transfer.DOI
Jiayue Chen, Hanyang Gu, Zhenqin Xiong, Da Liu (2018). Experimental investigation on heat transfer behavior in a tight 19 rod bundle cooled with supercritical R134a. Annals of Nuclear Energy.DOI
Da Liu, Hanyang Gu (2018). Study on heat transfer behavior in rod bundles with spacer grid. International Journal of Heat and Mass Transfer.DOI
Yong Mei, Shengjie Gong, Chi Wang, Hanyang Gu, Bingbin Ying, Yingxi Song (2017). Numerical simulation of drainage performance in a drain device of steam generator. Annals of Nuclear Energy.DOI
Shuo Chen, Zhenxiao Hu, Yao Xiao, Hanyang Gu (2017). Experimental investigation of subcooled flow boiling heat transfer in helical coils. Nuclear Engineering and Design.DOI
Yao Xiao, Zhenxiao Hu, Shuo Chen, Hanyang Gu (2017). Experimental study of two-phase frictional pressure drop of steam-water in helically coiled tubes with small coil diameters at high pressure. Applied Thermal Engineering.DOI
Zhenxiao Hu, Hanyang Gu (2017). Heat transfer of supercritical water in annuli with spacers. International Journal of Heat and Mass Transfer.DOI
Yong Mei, Yechen Zhu, Botao Zhang, Shengjie Gong, Hanyang Gu (2017). Effects of Heater Material and Surface Orientation on Heat Transfer Coefficient and Critical Heat Flux of Nucleate Boiling.DOI
Jiaqi Tao, Xing Jiang, Zhenqin Xiong, Hangyu Wu, Hanyang Gu (2017). Analysis on Heat Transfer of PRHR Heat Exchanger in Tank.DOI
Jinsong Pan, Yao Xiao, Hanyang Gu (2017). Numerical Investigation of Spacer Effects on Heat Transfer Enhancement in a Vertical Annular Channel at Supercritical Pressure.DOI
Da Liu, Fujun Gan, Chaozhu Zhang, Hanyang Gu (2017). Buoyancy Effect on Heat Transfer in 5×5 Rod Bundles.DOI
Zhenqin Xiong, Hanyang Gu, Siyu Zhang, Jiayue Chen (2017). Effect of intermittent heating on the heat transfer performance of supercritical R134a flowing in a pipe. Experimental Thermal and Fluid Science.DOI
Da Liu, Hanyang Gu (2017). Mixed convection heat transfer in a 5 × 5 rod bundles. International Journal of Heat and Mass Transfer.DOI
Hongbo Li, Zhenxiao Hu, Meng Zhao, Hanyang Gu, Donghua Lu (2017). Experimental investigation on transient heat transfer in 2 × 2 bundle during depressurization from supercritical pressure. Annals of Nuclear Energy.DOI
Hongbo Li, Meng Zhao, Zhenxiao Hu, Hanyang Gu, Donghua Lu (2017). Experimental study on transient heat transfer across critical pressure in 2 × 2 rod bundle with wire wraps. International Journal of Heat and Mass Transfer.DOI
Hongbo Li, Zhenxiao Hu, Donghua Lu, Gu Hanyang (2017). Experimental Investigation on Heat Transfer and Pressure Drop of Supercritical Water Flows in 2×2 Bundle With Wire Wraps.DOI
Da Liu, Hanyang Gu, Shengjie Gong (2016). The Spacer Grid Effect on Heat Transfer at Low Flow Rate in a 5×5 Rod Bundles.DOI
Hanyang Gu, Yong Mei, Chi Wang, Shengjie Gong, Binbin Ying, Yingxi Song (2016). An experimental investigation on drainage performance of a drain device in a steam generator of PWR. Progress in Nuclear Energy.DOI
Hanyang Gu, Chi Wang, Shengjie Gong, Yong Mei, Huang Li, Weimin Ma (2016). Investigation on contact angle measurement methods and wettability transition of porous surfaces. Surface and Coatings Technology.DOI
Gu Hanyang, Guo Liejin (2016). Modeling of bubble shape in horizontal and inclined tubes. Progress in Nuclear Energy.DOI
Jiayue Chen, Xiong Zhenqin, Yao Xiao, Gu Hanyang (2016). Experimental study on convective heat transfer of supercritical R134a in vertical circular tubes. Hedongli gongcheng.DOI
Zhenxiao Hu, Da Liu, Tao Jiaqi, Gu Hanyang (2016). Experimental study on heat transfer of supercritical water in 2 × 2 rod bundle with wrapped wire. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms.DOI
Hanyang Gu, Zhenxiao Hu, Da Liu, Hongbo Li, Meng Zhao, Xu Cheng (2015). Experimental study on heat transfer to supercritical water in 2×2 rod bundle with wire wraps. Experimental Thermal and Fluid Science.DOI
Shengjie Gong, Weimin Ma, Chi Wang, Yong Mei, Hanyang Gu (2015). An investigation on dynamic thickness of a boiling liquid film. International Journal of Heat and Mass Transfer.DOI
Zhenqin Xiong, Hanyang Gu, Shenjie Gong (2015). Experimental and numerical study on the flow pattern of the ADS windowless spallation target with a second free surface downstream using model fluid water. Nuclear Engineering and Design.DOI
Zhenqin Xiong, Minglu Wang, Hanyang Gu, Cheng Ye (2015). Experimental study on heat pipe heat removal capacity for passive cooling of spent fuel pool. Annals of Nuclear Energy.DOI
Hanyang Gu, Liejin Guo (2015). Bubble shape in horizontal and near horizontal intermittent flow. Annals of Nuclear Energy.DOI
Hanyang Gu, Xingliang Zhang, Shenjie Gong, Donghua Lu, Cheng Xu (2015). Experimental and numerical analysis of a new windowless target design of ADS. Annals of Nuclear Energy.DOI
Siyu Zhang, X. Cheng, Gu Hanyang (2015). Experimental study on heat transfer of supercritical freon flowing in vertical tube. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms.DOI
Zhenqin Xiong, Cheng Ye, Minglu Wang, Hanyang Gu (2014). Experimental study on the sub-atmospheric loop heat pipe passive cooling system for spent fuel pool. Progress in Nuclear Energy.DOI
Zhenqin Xiong, Hanyang Gu, Minglu Wang, Cheng Ye (2014). The thermal performance of a loop-type heat pipe for passively removing residual heat from spent fuel pool. Nuclear Engineering and Design.DOI
Siyu Zhang, Hanyang Gu, Cheng Xu, Zhenqin Xiong (2014). Experimental study on heat transfer of supercritical Freon flowing upward in a circular tube. Nuclear Engineering and Design.DOI
Shengjie Gong, Weimin Ma, Hanyang Gu (2014). An experimental investigation on bubble dynamics and boiling crisis in liquid films. International Journal of Heat and Mass Transfer.DOI
Siyu Zhang, Hanyang Gu, Zhenqin Xiong, Shengjie Gong (2014). Numerical investigation on heat transfer of supercritical fluid in a vertical 7-rod bundle. The Journal of Supercritical Fluids.DOI
Zhenqin Xiong, Mingchao Lu, Yazhou Li, Hanyang Gu, Cheng Xu (2013). Effects of the slots on the performance of swirl-vane separator. Nuclear Engineering and Design.DOI
Zhenqin Xiong, Mingchao Lu, Minglu Wang, Hanyang Gu, Cheng Xu (2013). Study on flow pattern and separation performance of air–water swirl-vane separator. Annals of Nuclear Energy.DOI
Hongbo Li, Meng Zhao, Hanyang Gu, Fei Wang, Jianmin Zhang, Yong Zhang, Jue Yang (2013). Experimental Research of Supercritical Water Heat Transfer in Different Channels.DOI
G. Zhang, Yanhua Yang, Hanyang Gu, Yang Yu (2013). Coolant distribution and mixing at the core inlet of PWR in a real geometry. Annals of Nuclear Energy.DOI
Gu Hanyang (2013). Numerical Analysis on Thermal-Hydraulic Behavior of Supercritical Fluid in 7-rod Bundles. Journal of Chinese Society of Power Engineering.
B.H. Yan, Hanyang Gu (2012). Effect of rolling motion on the expansion and contraction loss coefficients. Annals of Nuclear Energy.DOI
B.H. Yan, Hanyang Gu, Yu Lei (2012). Heat transfer of pulsating turbulent pipe flow in rolling motion. Progress in Nuclear Energy.DOI
Ge Zhang, Hao Zhang, Hanyang Gu, Yanhua Yang, X. Cheng (2012). Experimental and numerical investigation of turbulent convective heat transfer deterioration of supercritical water in vertical tube. Nuclear Engineering and Design.DOI
Guiyang Su, Hanyang Gu, Cheng Xu (2012). Experimental and numerical studies on free surface flow of windowless target. Annals of Nuclear Energy.DOI
B.H. Yan, Hanyang Gu, Yu Lei (2012). Effects of rolling motion on the flow and heat transfer of turbulent pulsating flow in channels. Progress in Nuclear Energy.DOI
Bing-Huo Yan, Hanyang Gu, L. Yu (2011). Numerical research of turbulent heat transfer in rectangular channels in ocean environment.DOI
B.H. Yan, G. Zhang, Hanyang Gu (2011). CFD analysis of the effect of rolling motion on the flow distribution at the core inlet. Annals of Nuclear Energy.DOI
B.H. Yan, G. Zhang, Hanyang Gu (2011). Theoretical analysis of the fluid mixing at the core inlet in rolling motion. Nuclear Engineering and Design.DOI
Donghua Lu, Hongbo Li, Binde Chen, Hanyang Gu (2011). Experimental study on the density wave oscillation in parallel rectangular channels with narrow gap. Annals of Nuclear Energy.DOI
B.H. Yan, Hanyang Gu (2011). CFD analysis of flow and heat transfer of turbulent pulsating flow in a tube in rolling motion. Annals of Nuclear Energy.DOI
Binghuo Yan, Hanyang Gu, Yanhua Yang, Yu Lei (2010). Theoretical models of turbulent flow in rolling motion. Progress in Nuclear Energy.DOI
Binghuo Yan, Hanyang Gu, Yanhua Yang, Yanping Huang (2010). The Flowing and Heat Transfer Models of Turbulent Flow in Rolling Motion. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Shanfang Huang, Tai-Yi Ma, Hanyang Gu, Yanhua Yang, Xiao Yan (2010). Heat Transfer Analysis in Mixed Convection. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Binghuo Yan, Hanyang Gu, Yanhua Yang, Yanping Huang (2010). CFD Analysis of Flowing Characteristics of Turbulent Flow in Rectangular Channels in Ocean Environment. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Yan Bing-huo, Gu Hanyang, Yanhua Yang, Yu Lei (2010). Numerical analysis of flowing characteristics of turbulent flow in rectangular channels in ocean environment. Progress in Nuclear Energy.DOI
顾汉洋，郭烈锦（2008）. 水平管内气液段塞流液塞发展特性实验研究(英文). Chinese Journal of Chemical Engineering.
Hanyang Gu, Liejin Guo (2008). Experimental Investigation of Slug Development on Horizontal Two-phase Flow. Chinese Journal of Chemical Engineering.DOI
Hanyang Gu, Cheng Xu, Xiaojing Liu (2008). Numerical Analysis of Thermal-Hydraulic Behavior of Supercritical Water in Vertical Upward/Downward Flow Channels. Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition.DOI
顾汉洋，郭烈锦（2007）. 水平和倾斜管内气液分层流界面稳定性(英文). Chinese Journal of Chemical Engineering.
Hanyang Gu, Liejin Guo (2007). Stability of Stratified Gas-Liquid Flow in Horizontal and Near Horizontal Pipes. Chinese Journal of Chemical Engineering.DOI
Gu Hanyang, Guo Liejin, Zhang Ximing, Wang Zhiwei (2007). Shape of isolated bubble in intermittent flows in a horizontal pipe. Heat Transfer-Asian Research.DOI
Xuejun Chen, Liejin GUO, Hanyang Gu, Xin Wang, Guangjun Li, Jinjia Wei (2005). Interfacial Waves and Slug Flow in Pipeline. Abstract of 5th International Symposium on Multiphase Flow and Heat Transfer and Energy Conversion.
顾汉洋，郭烈锦（2004）. 垂直圆管内湍流泡状流的数值研究. 《化工学报》.
顾汉洋，高晖，郭烈锦（2003）. 水平管油水两相分层紊流流动的数值研究. 《工程热物理学报》.
C. Zeng, Cong Shen, Xin Jin, Maolong Liu, Koji Okamoto, Li-Min Liu, Hanyang Gu. Transient thermal hydraulic analysis of a small passive lead–bismuth eutectic cooled fast reactor. Annals of Nuclear Energy.DOI
Shuo Chen, Zhen-Xiao Hu, Li Liu, Maolong Liu, Hanyang Gu. Development of a transient analysis code for trans-critical simulation of SCWR. Annals of Nuclear Energy.DOI
Maolong Liu, Ziyi Xu, Cong Shen, Feixi Zhang, Mengke Chao, Wei Zhang, Hanyang Gu. Calculation and experimental study on the flow instability behavior of a helically coiled steam generator. Annals of Nuclear Energy.DOI
数据集
Shuo Wang, Guanqun Ding, Yunbo Sun, Jiaming Shang, Junsen Fu, Yao Xiao, hanyang Gu (2026). Physics Informed Coarse Mesh Framework Predicts Oxidation Corrosion Deposition in Lead Bismuth Eutectic Systems. Shuo Wang et al. Zenodo (CERN European Organization for Nuclear Research).DOI