Ningyuan Wang, De-Qi Chen, Hanzhou Liu, Shan-Shan Bu, Hongxing Yu (2026). Prediction model for the initial dryout vapor quality in helically coiled tubes. Energy.DOI
Fenze Wang, Quan-Yao Ren, Hai-Dong Liu, Yi Xiao, Hongxing Yu, De-Qi Chen (2026). Experimental study on the characteristics of annular fluid film in a locally deformed narrow rectangular channel. Progress in nuclear energy (New series).DOI
Lei Zhong, Zefeng Wang, Hongxing Yu, Jian Deng, Chen Ling, Dong-Yong Wang (2025). Effect of surface oxidation on minimum film boiling temperature during Zr-4 quenching process. Annals of Nuclear Energy.DOI
Jun Xu, Hongxing Yu, Jian Deng, Yu Liu, Shu-Hua Ding, Mu-Hao Zhang, Xiaohui Xia (2025). Experimental study on startup performance of sodium heat pipe with high ratio of length-to-diameter under different coolant flow rates. Progress in nuclear energy (New series).DOI
Xue Zhang, Wenpei Feng, Xiaolong Yang, Hongxing Yu, Jian Deng, Si-Jia Du (2025). Investigation into the Flow and Heat Transfer Characteristics in Liquid Metal Cooled Narrow Rectangular Channel with Rough Surfaces. Case Studies in Thermal Engineering.DOI
Lei Zhong, Hongxing Yu, Chen Ling, De-Qi Chen, Jian Deng, Hai-Dong Liu, Jun Xu (2024). Study on the Improvement of RELAP5 Post-Critical Boiling Heat Transfer Model for the Submerged Cooling Process of Rectangular Channel. Volume 6: Thermal-Hydraulics and Safety Analysis.DOI
Xue Zhang, Hongxing Yu, Jian Deng, Si-Jia Du, Xiaoyu Wang, Wenpei Feng (2024). Study on the turbulent Prandtl number model for liquid metal flow and heat transfer in a narrow rectangular channel. Frontiers in Energy Research.DOI
Xue Zhang, Wenpei Feng, Hongxing Yu, Jian Deng, Si-Jia Du, Xiaoyu Wang (2024). Study on flow and heat transfer characteristics of liquid metal flow in narrow rectangular channels under high heat flux. Frontiers in Energy Research.DOI
Jun Xu, Hongxing Yu, Jian Deng, Yu Liu, Lu-Teng Zhang, Langlang Tian, Lei Zhong (2024). Study of Compressible Flow in Pipes Containing Mesh Structures. Volume 11: Student Paper Competition.DOI
Wenpei Feng, Shang-Dong Yang, Hongxing Yu, Xingqing Lu, Xue Zhang, Zhixing Gu (2024). Effect of Corrosion Behavior on the Heat Transfer Performance of Fuel Cladding in Lead-Cooled Fast Reactors. Volume 6: Thermal-Hydraulics and Safety Analysis.DOI
Yu-Gao Ma, Yingnan Zhang, Hongxing Yu, Shanfang Huang, Jian Deng, Xiao-qing Chai, Chang Zeng, Zhuohua Zhang (2023). Capillary Evaporating Film Model for a Screen-Wick Heat Pipe. Social Science Research Network.DOI
Zhi-Fang Qiu, Hongxing Yu, Qing-Wen Xiong, Xue-Wu Cao, Li-Li Tong (2023). Uncertainty and sensitivity analysis of the DVI line break loss of coolant accident for small modular reactor. Progress in nuclear energy (New series).DOI
Xue Zhang, Hongxing Yu, Jian Deng, Si-Jia Du, Xi-Lin Zhang, Z. Zou, Wenpei Feng, Yao-Xiang Zhang (2022). Investigation on the Simulation of Turbulent Heat Transfer of Liquid Metal Flow in a Narrow Rectangular Channel. Volume 8: Computational Fluid Dynamics (CFD) and Applications.DOI
Zhi-Xing Gu, Hongxing Yu, Jia-Ning Dai, Dai-Shun Huang, Ming-Yu Yan, Ya-Ou Shen, Chao Guo (2022). Code development of Single-phase 2-D pressure wave propagation. Annals of Nuclear Energy.DOI
Lei Zhong, De-Qi Chen, Hongxing Yu, Hai-Dong Liu, Ming-Jing Chen, Hanzhou Liu, Jian Deng, Shuhua Ding, Dan-yue Wu (2022). Experimental Study on Surface Characteristics and Thermal Conductivity of New Zirconium Alloy with Oxide Layer. Social Science Research Network.DOI
Li-Li Liu, Jian Deng, Ming Zhang, Liang Chen, Youyou Xu, Yuejian Luo, Y. Li, Hong-Ping Sun, Hongxing Yu, Hou-Jun Gong (2022). Analysis of 3-layer corium pool models in CISER2.0 code. Progress in nuclear energy (New series).DOI
Yu-Gao Ma, Jiusong Liu, Hongxing Yu, C. Tian, Shanfang Huang, Jian Deng, Xiao-Ming Chai, Yu Liu, Xiao-Qiang He (2022). Coupled irradiation-thermal-mechanical analysis of the solid-state core in a heat pipe cooled reactor. Nuclear Engineering and Technology.DOI
Yu-Gao Ma, Ruicheng Zhong, Hongxing Yu, Shanfang Huang, Changqing Tian, Xiao-Qiang He, Ze-Yu Ouyang, Jiusong Liu, Yu Liu, Xiao-Ming Chai (2022). Startup analyses of a megawatt heat pipe cooled reactor. Progress in nuclear energy (New series).DOI
Chao Guo, Pengcheng Zhao, Jian Deng, Hongxing Yu (2021). Safety Analysis of Small Modular Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100 Under Unprotected Transient. Frontiers in Energy Research.DOI
Yu-Gao Ma, Hongxing Yu, Shanfang Huang, Yingnan Zhang, Yu Liu, Chenglong Wang, Ruicheng Zhong, Xiao-Ming Chai, Cong-Rong Zhu, Xueqing Wang (2021). Effect of Inclination Angle on the Startup of a Frozen Sodium Heat Pipe. Applied Thermal Engineering.DOI
Ya-Ou Shen, S. Peng, Ming-Yu Yan, Yu Zhang, Jian Deng, Hongxing Yu, Dai-Shun Huang (2021). Analytical study of heat transfer for liquid metals in a turbulent tube flow.DOI
Yu-Gao Ma, Min-yun Liu, Erhui Chen, Biheng Xie, Xiao-Ming Chai, Shanfang Huang, Kan Wang, Hongxing Yu (2021). RMC/ANSYS MULTI-PHYSICS COUPLING SOLUTIONS FOR HEAT PIPE COOLED REACTORS ANALYSES. EPJ Web of Conferences.DOI
Li-Bo Qian, Jian Deng, Zhong-Chun Li, Wei Chen, Hongxing Yu, Yu-Fa Sun (2021). Theoretical research on two-phase flow instability in parallel channels under periodic heaving motion condition. Annals of Nuclear Energy.DOI
Yuxuan He, Hongxing Yu, Ren Yu, Jian Song, Hai-Bo Lian, Jiang-Yang He, Jiangtao Yuan (2021). A Correlation-Based Feature Selection Algorithm for Operating Data of Nuclear Power Plants. Science and Technology of Nuclear Installations.DOI
Yu-Gao Ma, Wenbin Han, Biheng Xie, Hongxing Yu, Min-yun Liu, Xiao-Qiang He, Shanfang Huang, Yu Liu, Xiao-Ming Chai (2021). Coupled neutronic, thermal-mechanical and heat pipe analysis of a heat pipe cooled reactor. Nuclear Engineering and Design.DOI
Yu-Gao Ma, Min-yun Liu, Biheng Xie, Wenbin Han, Hongxing Yu, Shanfang Huang, Xiao-Ming Chai, Yu Liu, Zhuohua Zhang (2021). Neutronic and thermal-mechanical coupling analyses in a solid-state reactor using Monte Carlo and finite element methods.DOI
Yu-Gao Ma, Changqing Tian, Hongxing Yu, Ruicheng Zhong, Zhuohua Zhang, Shanfang Huang, Deng Jian, Xiao-Ming Chai, Yun-young Yang (2021). Transient heat pipe failure accident analysis of a megawatt heat pipe cooled reactor.DOI
Ya-Ou Shen, S. Peng, Ming-Yu Yan, Yu Zhang, Jian Deng, Hongxing Yu, Dai-Shun Huang, Zhong-Chun Li (2021). Study of Flow and Heat Transfer Characteristics of Lead-Based Liquid Metals in a Turbulent Tube Flow and the Impacts of Roughness. Frontiers in Energy Research.DOI
Yuan-Ming Li, Quanyao Ren, Pan Yuan, G. Su, Hongxing Yu, Mei-yin Zheng, Haoyu Wang, Ying-Wei Wu, S. Ding (2020). Thermal-fluid-structure coupling analysis on plate-type fuel assembly under irradiation. Part-II Mechanical deformation and thermal-hydraulic characteristics. Nuclear Engineering and Technology.DOI
Yu-Gao Ma, Jinkun Min, Jin Li, Shichang Liu, Min-yun Liu, Xiao-Tong Shang, Gang Yu, Shanfang Huang, Hongxing Yu, Kan Wang (2020). Neutronics and thermal-hydraulics coupling analysis in accelerator-driven subcritical system. Progress in nuclear energy (New series).DOI
Yuan-Ming Li, Pan Yuan, Quanyao Ren, G. Su, Hongxing Yu, Haoyu Wang, Mei-yin Zheng, Ying-Wei Wu, S. Ding (2020). Thermal-fluid-structure coupling analysis for plate-type fuel assembly under irradiation. Part-I numerical methodology. Nuclear Engineering and Technology.DOI
Zhi-Gang Li, Wei Liu, Ming Pingzhou, P. An, Wei Lu, Junjie Pan, Dong Liu, Hongxing Yu (2020). The Sensitivity Analysis of the Core Lower Head Molten Pool Model Based on Variance Decomposition. Journal of Nuclear Engineering and Radiation Science.DOI
Yu-Gao Ma, Min-yun Liu, Wenbin Han, Biheng Xie, Xiao-Ming Chai, Shanfang Huang, Hongxing Yu (2020). Neutronic and Thermal-mechanical Coupling Schemes for Heat Pipe Cooled Reactor Designs. Journal of Nuclear Engineering and Radiation Science.DOI
Pei-Yi Li, Jian Deng, Lei Zhong, Li-Bo Qian, R. Cai, Yu-Gao Ma, Hongxing Yu (2020). Investigation of Turbulent Prt Model and the Segmentation Rule for LBE Turbulent Heat Transfer. Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation.DOI
Li-Li Liu, Hongxing Yu, Liang Chen, Jian Deng, Chun-Rui Deng, Ming Zhang, L. Hou (2019). A method for predicting the structure of corium pool in lower plenum of reactor vessel. Progress in nuclear energy (New series).DOI
Yu-Gao Ma, Shichang Liu, Zheng-Pei Luo, Shanfang Huang, Kaiwen Li, Kan Wang, Gang Yu, Hongxing Yu (2019). RMC/CTF multiphysics solutions to VERA core physics benchmark problem 9. Annals of Nuclear Energy.DOI
Liang Chen, Hongxing Yu, Li-Li Liu, Jian Deng, L. Hou, Hua-Ping Dong, Hang Zhang, Xiaoji Wang (2019). EFFECTS OF CORE PERIPHERAL COMPONENTS MELTING ON CORIUM POOL CONFIGURATION IN LOWER PLENUM OF ACP1000. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Pei-Yi Li, Hongxing Yu, Si-Jia Du, Ming-Yu Yan, Yu Liu, Ya-Ou Shen, Hong-Sheng Yuan, Xiao-Li Wu (2019). A NEW TURBULENT PRANDTL NUMBER MODEL FOR FORCED FULLY-DEVELOPED PIPE HEAT TRANSFER OF LIQUID METALS. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Yu-Gao Ma, Yinghuan Cui, Yisheng Hao, Shanfang Huang, Yanzhi Pan, Hongxing Yu (2019). NUMERICAL ANALYSES AND EXPERIMENTAL VERIFICATION ON MULTIPHASE FLOW MEASUREMENTS USING A GAMMA-RAY DENSITOMETER WITH BLIND-TEE MIXING. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Yu-Gao Ma, Ruicheng Zhong, Zhuohua Zhang, Xiao Chai, Shanfang Huang, Hongxing Yu (2019). A TRANSIENT AND STEADY-STATE NETWORK MODEL FORANNULAR-WICK HEAT PIPES IN CONTINUUM FLOW PATTERN. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Li-Li Liu, Hongxing Yu, Jian Deng, Liang Chen, Chun-Rui Deng, Qingan Xiang, Ling-Hong Wu (2019). Analysis of the configurations and heat transfer of corium pool in RPV lower plenum. Annals of Nuclear Energy.DOI
Fan Yang, S. Kudriakov, Studer Etienne, Zhi-Qiang Zou, Hongxing Yu (2016). Numerical Analysis of Hydrogen Risk Related Severe Accident Scenario in Chinese PWR.DOI
Li-Li Liu, Hongxing Yu, Jian Deng, Liang Chen, Ming Zhang, Dahuan Zhu (2016). Failure criterion of cladding oxide layer in dissolution mechanism.DOI
Dahuan Zhu, Qingan Xiang, Ming Zhang, Chun-Rui Deng, Jian Deng, Guangming Jiang, Hongxing Yu (2016). Evaluation of in-vessel corium retention margin for small modular reactor ACP100.DOI
Huan-Huan Peng, Hongxing Yu (2015). ICONE23-1263 STUDY ON HYDROGEN FLAME ACCELERATION AND DDT PROPERTIES AT ELEVATED TEMPERATURES AND PRESSURES.DOI
Li-Li Liu, Hongxing Yu, Jian Deng, Bin Chen, Ling-Hong Wu, Ming Zhang, Hang Zhang (2015). Method for calculating structure of molten pool in lower cap of pressure vessel in case of serious accident in reactor.
Xiao-Qiang He, Hongxing Yu, Guangming Jiang, Gao-Jian Dang, Dan Wu, Y. Zhang (2014). Cladding oxidation model development based on diffusion equations and a simulation of the monoclinic-tetragonal phase transformation of zirconia during transient oxidation.DOI
Hongxing Yu (2012). Study on Heat Transfer Prediction Models of Precursory Cooling Region in Reflooding Phase of Tight Lattice.
Dan Wu, Hongxing Yu, Jun-Chong Yu, Jie Li, Ji-Yang Yu (2012). Development of a New Heat Transfer Model Near the Quench Front in the Reflooding Phase of a Tight Lattice.DOI
Dan Wu, Hongxing Yu, Jun-Chong Yu, Ji-Yang Yu (2012). Reflooding characteristics investigation and predicted models improvement for the pressurized water reactor with the tight lattice core design.DOI