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Hongxing Yu
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Proceedings Papers

Development of Quench Analysis Program Based on ARSAC

Lei Zhong, Hongxing Yu, Deqi Chen, Hanzhou Liu, Jian Deng, Dan Wu
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A062, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92080
https://doi.org/10.1115/ICONE29-92080
View Paper titled, Development of Quench Analysis Program Based on ARSAC
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Topics: Boiling, China, Cladding systems (Building), Film boiling, Fuels, Heat transfer, Nuclear reactors, Oxidation, Quenching (Metalworking), Temperature
Proceedings Papers

Investigation on the Simulation of Turbulent Heat Transfer of Liquid Metal Flow in a Narrow Rectangular Channel

Xue Zhang, Hongxing Yu, Jian Deng, Sijia Du, Xilin Zhang, Ziqiang Zou, Wenpei Feng, Yaoxiang Zhang
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A046, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92595
https://doi.org/10.1115/ICONE29-92595
View Paper titled, Investigation on the Simulation of Turbulent Heat Transfer of Liquid Metal Flow in a Narrow Rectangular Channel
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Topics: Flow (Dynamics), Heat transfer, Liquid metals, Simulation, Turbulent heat transfer
Journal Articles

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

Yugao Ma, Minyun Liu, Biheng Xie, Wenbin Han, Xiaoming Chai, Shanfang Huang, Hongxing Yu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021303.
Paper No: NERS-20-1207
https://doi.org/10.1115/1.4051612
Published Online: October 19, 2021
View Article titled, Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs
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Topics: Design, Displacement, Fuels, Geometry, Heat, Heat pipes, Molten salt reactors, Nuclear fission, Pipes, Temperature
Proceedings Papers

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe Cooled Reactor Designs

Yugao Ma, Minyun Liu, Wenbin Han, Biheng Xie, Xiaoming Chai, Shanfang Huang, Hongxing Yu
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A006, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16100
https://doi.org/10.1115/ICONE2020-16100
View Paper titled, Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe Cooled Reactor Designs
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Topics: Heat pipes, Feedback, Geometry, Heat transfer, Construction, Design, Finite element analysis, Finite element methods, High temperature, Light water reactors
Proceedings Papers

Analysis and Parallel Implementation of Transient Thermal Feedback in Neutron Kinetics Calculation

Pingzhou Ming, Zhigang Li, Ping An, Wei Lu, Dong Liu, Hongxing Yu
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A039, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81442
https://doi.org/10.1115/ICONE26-81442
View Paper titled, Analysis and Parallel Implementation of Transient Thermal Feedback in Neutron Kinetics Calculation
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Topics: Feedback, Neutrons, Transients (Dynamics), Pressurized water reactors, Computer software, Interpolation, Runge-Kutta methods
Journal Articles

Parallel Analysis of Linear Systems in CORTH and KYLIN2

Pingzhou Ming, Dingyong Chen, Bin Wu, Wei Lu, Dong Liu, Hongxing Yu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031010.
Paper No: NERS-17-1143
https://doi.org/10.1115/1.4039036
Published Online: May 16, 2018
View Article titled, Parallel Analysis of Linear Systems in CORTH and KYLIN2
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Topics: Linear systems, Thermal hydraulics, Manufacturing, Cores (Molding materials)
Proceedings Papers

The Linear System Solver of Programs Named CORTH and KYLIN2

Pingzhou Ming, Junjie Pan, Xiaolan Tu, Dong Liu, Hongxing Yu
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A042, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67222
https://doi.org/10.1115/ICONE25-67222
View Paper titled, The Linear System Solver of Programs Named CORTH and KYLIN2
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Topics: Linear systems, China, Manufacturing, Nuclear power, Thermal hydraulics
Proceedings Papers

Numerical Analysis of Hydrogen Risk Related Severe Accident Scenario in Chinese PWR

Yang Fan, Sergey Kudriakov, Studer Etienne, Zou Zhiqiang, Hongxing Yu
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T13A012, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60671
https://doi.org/10.1115/ICONE24-60671
View Paper titled, Numerical Analysis of Hydrogen Risk Related Severe Accident Scenario in Chinese PWR
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Topics: Accidents, Hydrogen, Numerical analysis, Pressurized water reactors, Risk, Combustion, Containment, Pressure, Stress, Computational fluid dynamics
Proceedings Papers

Development of a New Heat Transfer Model Near the Quench Front in the Reflooding Phase of a Tight Lattice

Dan Wu, Hongxing Yu, Junchong Yu, Jie Li, Jiyang Yu
Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 227-234, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54338
https://doi.org/10.1115/ICONE20-POWER2012-54338
View Paper titled, Development of a New Heat Transfer Model Near the Quench Front in the Reflooding Phase of a Tight Lattice
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Topics: Evaporation, Heat transfer, Transients (Dynamics), Temperature, Boiling, Liquid films, Heat, Vapors
Proceedings Papers

Reflood Oxidation Model Based on Reaction-Diffusion Equations

Xiaoqiang He, Hongxing Yu, Guangming Jiang
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 981-990, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30030
https://doi.org/10.1115/ICONE18-30030
View Paper titled, Reflood Oxidation Model Based on Reaction-Diffusion Equations
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Topics: Diffusion (Physics), Oxidation
Proceedings Papers

On the Use of Binary Importance Decision for Risk-Informed Categorization of SSCs

Wei Zeng, Hongxing Yu
Proc. ASME. ICONE17, Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications, 323-329, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75071
https://doi.org/10.1115/ICONE17-75071
View Paper titled, On the Use of Binary Importance Decision for Risk-Informed Categorization of SSCs
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Topics: Risk