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Wenbin Han
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Journal Articles

Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel

Wenbin Han, Jian Deng, Qi Lu, Chong Chen, Youyou Xu, Tao Zhang, Shanfang Huang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041104.
Paper No: NERS-22-1145
https://doi.org/10.1115/1.4062119
Published Online: April 17, 2023
View Article titled, Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel
Open the PDF for Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel in another window
Topics: Additive manufacturing, Computational fluid dynamics, Design, Fuels, Particulate matter, Temperature, Coolants, Neutrons, Heat transfer, Computer software
Proceedings Papers

Neutronic and Thermal-Hydraulic Analyses for an Additive Manufacturing Reactor Core With SiC Matrix and TRISO Particle Fuel

Wenbin Han, Jian Deng, Qi Lu, Chong Chen, Youyou Xu, Tao Zhang, Shanfang Huang
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A102, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92655
https://doi.org/10.1115/ICONE29-92655
View Paper titled, Neutronic and Thermal-Hydraulic Analyses for an Additive Manufacturing Reactor Core With SiC Matrix and TRISO Particle Fuel
Open the PDF for Neutronic and Thermal-Hydraulic Analyses for an Additive Manufacturing Reactor Core With SiC Matrix and TRISO Particle Fuel in another window
Topics: Additive manufacturing, Computational fluid dynamics, Design, Fuels, Particulate matter
Proceedings Papers

A High-Temperature Gas-Cooled Reactor Simulation System and Its Application Based on VPOWER Platform

Biheng Xie, Chengzhi Ji, Xiaoyu Guo, Wenbin Han, Yisheng Hao, Junyi Chen, Shanfang Huang, Kan Wang, Hongbin Wei, Yanming Liang
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A020, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64532
https://doi.org/10.1115/ICONE28-64532
View Paper titled, A High-Temperature Gas-Cooled Reactor Simulation System and Its Application Based on VPOWER Platform
Open the PDF for A High-Temperature Gas-Cooled Reactor Simulation System and Its Application Based on VPOWER Platform in another window
Topics: Simulation, Teaching, Very high temperature reactors, Accidents, Nuclear engineering, Nuclear industry, Students, Boilers, Control systems, Design
Proceedings Papers

A Sodium-Cooled Fast Reactor Simulation System and its Application In Teaching Research Based on VPOWER Platform

Chengzhi Ji, Biheng Xie, Xiaoyu Guo, Wenbin Han, Yisheng Hao, Junyi Chen, Shanfang Huang, Kan Wang, Hongbin Wei, Yanming Liang
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T01A005, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64364
https://doi.org/10.1115/ICONE28-64364
View Paper titled, A Sodium-Cooled Fast Reactor Simulation System and its Application In Teaching Research Based on VPOWER Platform
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Topics: Simulation, Sodium fast reactors, Teaching
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

An Effective Viscosity Equation for the CFD Analysis of the Micro Flows in the Confinement Ring

Yuanhao Wu, Ling Tian, Wenbin Han
Proc. ASME. IMECE2014, Volume 7: Fluids Engineering Systems and Technologies, V007T09A064, November 14–20, 2014
Publisher: American Society of Mechanical Engineers
Paper No: IMECE2014-37686
https://doi.org/10.1115/IMECE2014-37686
View Paper titled, An Effective Viscosity Equation for the CFD Analysis of the Micro Flows in the Confinement Ring
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Topics: Computational fluid dynamics, Flow (Dynamics), Viscosity, Engineers, Engineering simulation, Simulation, Errors, Gases, Plasma etching, Product design