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Proceedings Papers

Analysis of Transient Corium Pool Structure in the Lower Plenum of Reactor Vessel

Liang Chen, Hua Pang, Ximing Xie, Lei Zhong, Rong Cai
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A041, August 4–5, 2020
Paper No: ICONE2020-16470
DOI: https://doi.org/10.1115/ICONE2020-16470
View Paper titled, Analysis of Transient Corium Pool Structure in the Lower Plenum of Reactor Vessel
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Topics: Accidents, Reactor vessels, Transients (Dynamics), Vessels, Density, Heat flux, Heavy metals, China, Coolants, Critical heat flux
Proceedings Papers

A Theoretical Model of the Stress Intensity Factor Threshold of DHC for Fuel Cladding Tube

Liang Chen, Lili Liu, Xiaoming Song, Hua Pang
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A031, July 22–26, 2018
Paper No: ICONE26-81665
DOI: https://doi.org/10.1115/ICONE26-81665
View Paper titled, A Theoretical Model of the Stress Intensity Factor Threshold of DHC for Fuel Cladding Tube
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Topics: Cladding systems (Building), Fuels, Stress, Temperature, Fracture (Materials), Temperature gradient, Cracking (Materials), Diffusion (Physics), Fracture (Process), Hydrogen
Journal Articles

Numerical Simulation Research on the Performance of SCWR Fuel Rod

Changbing Tang, Shuo Xing, Hua Pang, Ping Chen, Yi Zhou
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011014.
Paper No: NERS-17-1029
DOI: https://doi.org/10.1115/1.4038060
Published Online: December 4, 2017
View Article titled, Numerical Simulation Research on the Performance of SCWR Fuel Rod
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Topics: Cladding systems (Building), Computer simulation, Fuel rods, Fuels, Irradiation (Radiation exposure), Stainless steel, Supercritical water reactors, Temperature, Thermal expansion, Thermal conductivity
Proceedings Papers

Simulation of the Delayed Hydride Cracking Velocity for Zirconium Alloy Materials Considering Irradiation Effects

Jingyu Zhang, Bingzhong Wang, Jiacheng Zhu, Shurong Ding, Liang Chen, Wenjie Li, Hua Pang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A055, July 2–6, 2017
Paper No: ICONE25-67410
DOI: https://doi.org/10.1115/ICONE25-67410
View Paper titled, Simulation of the Delayed Hydride Cracking Velocity for Zirconium Alloy Materials Considering Irradiation Effects
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Topics: Cracking (Materials), Irradiation (Radiation exposure), Simulation, Zirconium alloys, Embrittlement, Hardening, Traction, Anisotropy, Boundary-value problems, Computer simulation
Proceedings Papers

The Method of Specific Heat Capacity Measurement for Irradiated Zr-4 Alloy Capsule Material

Liang Chen, Hua Pang, Xiaoming Song, Lili Liu, Wenjie Li, Changbing Tang
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, V001T03A008, June 26–30, 2016
Paper No: ICONE24-60141
DOI: https://doi.org/10.1115/ICONE24-60141
View Paper titled, The Method of Specific Heat Capacity Measurement for Irradiated Zr-4 Alloy Capsule Material
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Topics: Alloys, Specific heat, Zirconium, China, Computer software, Differential scanning calorimetry, Temperature, Vents
Proceedings Papers

Probability Analysis of the Fuel Microsphere Distribution of Dispersion-Type Nuclear Fuel Plates

Lijun Gao, Hua Pang, Bingde Chen, Shengyao Jiang, Jiyang Yu, Zhong Xiao
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 59-67, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54154
DOI: https://doi.org/10.1115/ICONE20-POWER2012-54154
View Paper titled, Probability Analysis of the Fuel Microsphere Distribution of Dispersion-Type Nuclear Fuel Plates
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Topics: Fuels, Nuclear fuels, Plates (structures), Probability, Cylinders, Fracture (Materials), Gaussian distribution, Disperse systems, Irradiation (Radiation exposure), Metals
eBook Chapter

A Web Mining Based Distributed Education Resources Recommendation System

Series: ASME Press Select Proceedings
Publisher: ASME Press
Published: 2012
ISBN: 9780791859971
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Topics: Education, Mining