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Proceedings Papers

Modeling of Irradiation-Induced Thermo-Mechanical Coupling Behavior in Metal Matrix Microencapsulated Fuel

Hongyang Wei, Fawen Zhu, Jun Ru, Haoyu Wang, Jing Zhang, Hua Li, Yun Li, Chunlan Huang, Yuanming Li, Shurong Ding
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A016, August 4–6, 2021
Paper No: ICONE28-65563
https://doi.org/10.1115/ICONE28-65563
View Paper titled, Modeling of Irradiation-Induced Thermo-Mechanical Coupling Behavior in Metal Matrix Microencapsulated Fuel
Open the PDF for Modeling of Irradiation-Induced Thermo-Mechanical Coupling Behavior in Metal Matrix Microencapsulated Fuel in another window
Topics: Finite element analysis, Fuels, Irradiation (Radiation exposure), Metals, Modeling, Thermomechanics
Proceedings Papers

Effect of Fuel Meat Thickness on the Non-Uniform Irradiation-Induced Thermo-Mechanical Behavior in Monolithic UMo/Al Fuel Plates

Feng Yan, Yunmei Zhao, Shurong Ding
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A057, July 2–6, 2017
Paper No: ICONE25-67531
https://doi.org/10.1115/ICONE25-67531
View Paper titled, Effect of Fuel Meat Thickness on the Non-Uniform Irradiation-Induced Thermo-Mechanical Behavior in Monolithic UMo/Al Fuel Plates
Open the PDF for Effect of Fuel Meat Thickness on the Non-Uniform Irradiation-Induced Thermo-Mechanical Behavior in Monolithic UMo/Al Fuel Plates in another window
Topics: Fuels, Irradiation (Radiation exposure), Plates (structures), Thermomechanics, Stress, Algorithms, Constitutive equations, Deformation, Density, Design
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
https://doi.org/10.1115/ICONE25-67410
View Paper titled, Simulation of the Delayed Hydride Cracking Velocity for Zirconium Alloy Materials Considering Irradiation Effects
Open the PDF for Simulation of the Delayed Hydride Cracking Velocity for Zirconium Alloy Materials Considering Irradiation Effects in another window
Topics: Cracking (Materials), Irradiation (Radiation exposure), Simulation, Zirconium alloys, Embrittlement, Hardening, Traction, Anisotropy, Boundary-value problems, Computer simulation
Proceedings Papers

Effects of Irradiation Growth on the Thermo-Mechanical Behaviors Evolution in Inert Matrix Fuel Elements

Xin Gong, Yunmei Zhao, Shurong Ding, Yongzhong Huo, Lin Zhang, Yuanming Li
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A023, July 29–August 2, 2013
Paper No: ICONE21-15791
https://doi.org/10.1115/ICONE21-15791
View Paper titled, Effects of Irradiation Growth on the Thermo-Mechanical Behaviors Evolution in Inert Matrix Fuel Elements
Open the PDF for Effects of Irradiation Growth on the Thermo-Mechanical Behaviors Evolution in Inert Matrix Fuel Elements in another window
Topics: Damage, Fuels, Irradiation (Radiation exposure), Thermomechanics