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Proceedings Papers

Investigation and Design of Energy-Absorbing Structure in Nuclear Fuel Cask

Yuchen Hao, Yue Li, Jinhua Wang, Bin Wu, Tao Ma, Haitao Wang
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T11A007, August 4–6, 2021
Paper No: ICONE28-63388
DOI: https://doi.org/10.1115/ICONE28-63388
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Topics: Design, Nuclear fuels, Transportation systems, Fuels, Metals, Safety, High temperature, Construction, Containers, Economics
Proceedings Papers

Probability of Rupture for WWER-1000 Main Piping

Yaroslav Dubyk, Maksym Zarazovskii, Sergii Ageiev, Vladislav Filonov
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A014, August 4–5, 2020
Paper No: ICONE2020-16897
DOI: https://doi.org/10.1115/ICONE2020-16897
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Topics: Leakage, Pipes, Probability, Rupture, Stress, Fracture (Materials), Accounting, Flow (Dynamics), Fracture toughness, Nuclear power stations
Proceedings Papers

Finite Element Model to Simulate the Spacer Grid Buckling Characteristics

Youngik Yoo, Joongjin Kim, Kyongbo Eom, Hyeongkoo Kim
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T05A002, August 4–5, 2020
Paper No: ICONE2020-16082
DOI: https://doi.org/10.1115/ICONE2020-16082
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Topics: Buckling, Finite element model, Fuel rods, Manufacturing, Mechanical behavior, Nuclear fuels, Compression, Drag (Fluid dynamics), Impact testing, Mechanical properties
Proceedings Papers

The Experimental Research on the Mechanical Characteristics of the Newly Designed Fuel Rod Supporting Structure of Spacer Grid

Quan-yao Ren, Zeng-ping Pu, Mei-yin Zheng, Jie Chen, Mian Qin, Yuan-Ji Han, Yuan Peng, Ping Chen, Rui-rui Zhao, Jian-wei Li
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T05A004, August 4–5, 2020
Paper No: ICONE2020-16121
DOI: https://doi.org/10.1115/ICONE2020-16121
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Topics: Deformation, Fuel rods, Mechanical properties, Springs, Stress, Deflection, Manufacturing, Neutron flux, Strips
Proceedings Papers

Evaluation of Irradiation Embrittlement of the Weld Metals in the Chinese RPV

Yupeng Cao, Yinbiao He, Yifeng Huang, Binxi Wang, Yan Yu, Hui Li, Hu Hui
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T09A003, August 4–5, 2020
Paper No: ICONE2020-16261
DOI: https://doi.org/10.1115/ICONE2020-16261
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Topics: Embrittlement, Irradiation (Radiation exposure), Metals, Forging, Mechanical properties, China, Damage, Design, Fluence (Radiation measurement), Fracture toughness
Proceedings Papers

Multiphysics Modeling of Thorium-Based (Th, U)O 2 and (Th, Pu)O 2 Fuel Performance in a Light Water Reactor

Rong Liu, Jie-Jin Cai, Wen-Zhong Zhou, Ye Wang
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A012, July 22–26, 2018
Paper No: ICONE26-81237
DOI: https://doi.org/10.1115/ICONE26-81237
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Topics: Fuels, Light water reactors, Modeling, Temperature, Nuclear fission, Pressure, Mechanical properties, Nuclear reactors
Proceedings Papers

Analysis on the Dynamic Buckling Behavior of the Spacer Grid Structure

Yan Guo, Chenglong Gu, Wei Tian, Weicai Li
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A048, July 22–26, 2018
Paper No: ICONE26-82298
DOI: https://doi.org/10.1115/ICONE26-82298
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Topics: Buckling, Design, Fuels, Manufacturing, Mechanical properties, Pressurized water reactors, Stiffness, Stress, Structural elements (Construction), Vibration
Proceedings Papers

Additive Manufacturing of Spent Fuel Storage Rack Model by Selective Laser Melting

Xiaoming He, Ziqiang Zhu, Changlei Shao, Ran Huang
Proc. ASME. NUCLRF2018, ASME 2018 Nuclear Forum, V001T02A001, June 24–28, 2018
Paper No: NUCLRF2018-7409
DOI: https://doi.org/10.1115/NUCLRF2018-7409
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Topics: Additive manufacturing, Lasers, Melting, Spent fuel storage, Manufacturing, Stainless steel, Economics , Mechanical properties, Nuclear power stations, Safety
Proceedings Papers

Dynamic Seismic Response Analysis of Nuclear Storage Tank Based on Fluid-Structure Coupling Method

Yu Weng, Lang Liu, Yang Jiang, Hongfang Gu, Haijun Wang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A064, July 2–6, 2017
Paper No: ICONE25-66835
DOI: https://doi.org/10.1115/ICONE25-66835
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Topics: Fluids, Storage tanks, Computational fluid dynamics, Finite element methods, Flow (Dynamics), Displacement, Earthquakes, Stress, Vessels, Turbulence
Proceedings Papers

Small Punch Test on Mechanical Properties of Molybdenum Single Crystal Weld

Yan Ma, Jianju Wang, Jinyun Lei
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A033, July 2–6, 2017
Paper No: ICONE25-66824
DOI: https://doi.org/10.1115/ICONE25-66824
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Topics: Crystals, Mechanical properties, Molybdenum, Displacement, Stress, Yield strength, Brittleness, Creep, Electron beam welding, Embrittlement
Proceedings Papers

Preparation and Properties Investigation of Neutron Absorber Material Mo-Tb-Dy and Y-Tb-Dy Alloys

Junqiang Lu, Lei Chen, Congzhang Qiu, Weiyan Yang, Feifei Zhang, Ruifang Yang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A026, July 2–6, 2017
Paper No: ICONE25-66747
DOI: https://doi.org/10.1115/ICONE25-66747
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Topics: Alloys, Neutrons, Irradiation (Radiation exposure), Temperature, Corrosion, Atoms, Corrosion resistance, Density, Diluents, Displacement
Proceedings Papers

Simulation of Behaviors of a One-Third Scale Containment Model Test

Guopeng Ren, Rong Pan, Feng Sun
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A113, July 2–6, 2017
Paper No: ICONE25-67779
DOI: https://doi.org/10.1115/ICONE25-67779
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Topics: Containment, Simulation, Tendons, Concretes, Finite element model, Pressure, Deformation, Nuclear power stations, Design, Safety
Proceedings Papers

Investigation Into the Influence of Fuel Rods on the Anti-Seismic Mechanical Characteristics of Fuel Assembly Spacer Grid by FEM Method

Jingya Sun, Yu Dang, Song Liu, Jiazheng Liu, Libing Zhu
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A052, July 2–6, 2017
Paper No: ICONE25-67362
DOI: https://doi.org/10.1115/ICONE25-67362
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Topics: Finite element methods, Finite element model, Fuel rods, Fuels, Manufacturing, Mechanical properties, Springs, Deflection, Friction, Simulation
Proceedings Papers

Effects of Neutron Irradiation on the Mechanical and Electromagnetic Properties of Reactor Pressure Vessel Steels

Li Chengliang, Shu Guogang, Chen Jun, Liu Yi, Liu Wei, Hu Yichuan, Duan Yuangang, Liu Feihua
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A013, July 2–6, 2017
Paper No: ICONE25-66464
DOI: https://doi.org/10.1115/ICONE25-66464
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Topics: Irradiation (Radiation exposure), Neutrons, Reactor vessels, Steel, Damage, Electrical resistivity, Ductility, Failure mechanisms, Fracture toughness, Magnetization
Proceedings Papers

Microstructure and Properties of New Zirconium Alloys for CAP1400 Fuel Assembly

Qifeng Zeng, Libing Zhu, Gaihuan Yuan, Lian Wang, Guocheng Sun, Junqiang Lu
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A037, July 2–6, 2017
Paper No: ICONE25-66951
DOI: https://doi.org/10.1115/ICONE25-66951
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Topics: Fuels, Manufacturing, Zirconium alloys, Alloys, Corrosion resistance, Creep, Mechanical properties, Design, Temperature, Water chemistry
Proceedings Papers

Microstructures and Properties of 304L Steel CAP1400 Fuel Bottom Nozzles Prepared by Additive Manufacturing Technology

Li Zongshu, Liu Wentao, Yang Songtao, Hao Ruotong
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A046, July 2–6, 2017
Paper No: ICONE25-67213
DOI: https://doi.org/10.1115/ICONE25-67213
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Topics: Additive manufacturing, Fuels, Nozzles, Steel, Manufacturing, Lasers, Fracture (Materials), Fracture (Process), Ferrites (Magnetic materials), Mechanical properties
Proceedings Papers

Tungsten Powder Filled Polymers for Flexible Radiation Shields in Nuclear Industries

Binyou Yan, Jiupeng Song, Wei Wang, Yang Yu
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A027, July 2–6, 2017
Paper No: ICONE25-67382
DOI: https://doi.org/10.1115/ICONE25-67382
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Topics: Filled polymers, Nuclear industry, Radiation (Physics), Tungsten, Pipes, Composite materials, Density, Mechanical properties, Polymers, Shapes
Proceedings Papers

Investigation on Deposited Metal Properties of Homemade Nickel and Nickel-Free Electrodes and Fluxes for Submerged Arc Welding of SA-508 Gr.3 Cl.1

Le Mei, Junbao Zhang, Yifeng Huang, Yan Yu, Yong Jiang, Qifan Liu, Xiaoning Zhang, Yu Gu
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A034, July 2–6, 2017
Paper No: ICONE25-66331
DOI: https://doi.org/10.1115/ICONE25-66331
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Topics: Arc welding, Electrodes, Flux (Metallurgy), Metals, Nickel, Irradiation (Radiation exposure), Mechanical properties, Protons, Dislocations, Ferrites (Magnetic materials)
Proceedings Papers

Mechanical Characteristics of Nuclear Main Steam Line Penetration Fabricated by Electric Melting Additive Manufacturing

Xiaoming He, Xiaoning Zhang, Yongdong Wang, Yiqing Wang, Dong Ning
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A035, July 2–6, 2017
Paper No: ICONE25-66332
DOI: https://doi.org/10.1115/ICONE25-66332
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Topics: Additive manufacturing, Mechanical properties, Melting, Steam, Manufacturing, Aerospace industry, Biomedicine, Computer-aided design, Economics , Nuclear power stations
Proceedings Papers

An Image-Based Micro-Scale Fracture Model for Weld Zone in Nuclear Pipe and Component

Xiaoming Bai, Liangang Zheng, Xinjun Wang, Xi Lv
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A047, July 2–6, 2017
Paper No: ICONE25-66441
DOI: https://doi.org/10.1115/ICONE25-66441
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Topics: Fracture (Materials), Fracture (Process), Microscale devices, Pipes, Finite element analysis, Boundary-value problems, Damping, Engineering standards, Materials properties, Mechanical properties