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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
Journal Articles

Hybrid Reactivity-Equivalent Physical Transformation Method on Double-Heterogeneous System Containing Dispersed Fuel Particles and Burnable Poison Particles

Lei Lou, Xiaoming Chai, Dong Yao, Xingjie Peng, Mancang Li, Liang Chen, Yingrui Yu, Lianjie Wang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021601.
Paper No: NERS-20-1025
https://doi.org/10.1115/1.4051724
Published Online: October 19, 2021
View Article titled, Hybrid Reactivity-Equivalent Physical Transformation Method on Double-Heterogeneous System Containing Dispersed Fuel Particles and Burnable Poison Particles
Open the PDF for Hybrid Reactivity-Equivalent Physical Transformation Method on Double-Heterogeneous System Containing Dispersed Fuel Particles and Burnable Poison Particles in another window
Topics: Fuels, Particulate matter
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
Open the PDF for Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe Cooled Reactor Designs in another window
Topics: Heat pipes, Feedback, Geometry, Heat transfer, Construction, Design, Finite element analysis, Finite element methods, High temperature, Light water reactors
Journal Articles

The Powerful Method of Characteristics Module in Advanced Neutronics Lattice Code KYLIN-2

Xiaoming Chai, Xiaolan Tu, Wei Lu, Zongjian Lu, Dong Yao, Qing Li, Wenbin Wu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2017, 3(3): 031004.
Paper No: NERS-16-1110
https://doi.org/10.1115/1.4035934
Published Online: May 25, 2017
View Article titled, The Powerful Method of Characteristics Module in Advanced Neutronics Lattice Code KYLIN-2
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Topics: Boundary-value problems, Reflection, Trajectories (Physics), Geometry, Rotation
Proceedings Papers

The Powerful MOC Module in Advanced Neutronics Lattice Code GALAXY

Xiaoming Chai, Xiaolan Tu, Wei Lu
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A025, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60661
https://doi.org/10.1115/ICONE24-60661
View Paper titled, The Powerful MOC Module in Advanced Neutronics Lattice Code GALAXY
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Topics: Boundary-value problems, China, Computation, Geometry, Neutrons, Nuclear power, Shapes, Trajectories (Physics)