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Proceedings Papers

A Comparative Approach of a Seismic Response Analysis Based on Housner Model and Added Mass Model for a Nuclear Water Storage Tank

Chengzhuo Yang, Thomas Metais, Zihao Zheng, Yang Dai, Jiesheng Min
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A070, August 8–12, 2022
Paper No: ICONE29-93230
DOI: https://doi.org/10.1115/ICONE29-93230
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Topics: Water, Water storage, Sloshing, Fluid structure interaction, Center of mass, Convection, Displacement, Dynamic response, Finite element analysis, Finite element model
Proceedings Papers

Preliminary Study on Corrosion Behavior and Mechanical Properties Of Inconel 617 in Impure Helium Environment of VHTR

Bin Du, Huaqiang Yin, Tao Ma, Haoxiang Li, Wei Zheng, Xuedong He
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A003, August 8–12, 2022
Paper No: ICONE29-88943
DOI: https://doi.org/10.1115/ICONE29-88943
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Topics: Corrosion, Helium, Mechanical properties, Very high temperature reactors
Proceedings Papers

A Detailed Model to Predict Mechanical Characteristics of Fuel Assembly

Jingjing Zhao, Shiyin Xu, Wenan Pan, Jingya Sun, Yuxi Du
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A043, August 8–12, 2022
Paper No: ICONE29-91931
DOI: https://doi.org/10.1115/ICONE29-91931
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Topics: Fuels, Manufacturing, Mechanical properties
Proceedings Papers

Study on Properties of Aging and Immersion in Boric Acid Water of PEEK Insulation Material

Jing An, Shan Jin, Li-Qin Zhang, Hao Wu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A093, August 8–12, 2022
Paper No: ICONE29-93867
DOI: https://doi.org/10.1115/ICONE29-93867
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Topics: Insulation, Mechanical properties, Water
Proceedings Papers

Microstructure, Texture and Mechanical Properties in Different Deformation Regions of the Compressed Zr-4 Alloy With Lamellar Structure

Jie Ren, Geping Li, Fusen Yuan, Ben Wang, Fuzhou Han, Muhammad Ali, Yingdong Zhang, Wenbin Guo, Bo Gao
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A027, August 8–12, 2022
Paper No: ICONE29-92283
DOI: https://doi.org/10.1115/ICONE29-92283
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Topics: Alloys, Deformation, Mechanical properties, Recrystallization, Texture (Materials), Zirconium
Proceedings Papers

The Research on Welding Procedure and Performance of Zr-3 Thick Plate

Yu Gao, Xiaoru Liang, Yuxin Wang, Lifeng Guo
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A021, August 8–12, 2022
Paper No: ICONE29-92037
DOI: https://doi.org/10.1115/ICONE29-92037
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Topics: Corrosion resistance, Heat treating (Metalworking), Mechanical properties, Welding, Zirconium
Proceedings Papers

Study on the Manufacturing Process of Large Super Alloy X-750 Forgings for Nuclear Equipment

Mei-fang Chen, Sheng-qiang Cao, Kai Dong
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A019, August 8–12, 2022
Paper No: ICONE29-91791
DOI: https://doi.org/10.1115/ICONE29-91791
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Topics: Alloys, Forging, Forgings (Products), Manufacturing, Springs, Temperature, Grain size, Annealing, Creep, Fracture (Materials)
Proceedings Papers

Codes Comparative Study on Mechanical Properties of Core Forgings of Reactor Pressure Vessel

Hao Yu, Yinbiao He, Xinxin Wu, Shenjie Gu, Xin Liu, Hongchang Wang
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A003, August 8–12, 2022
Paper No: ICONE29-90363
DOI: https://doi.org/10.1115/ICONE29-90363
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Topics: Forgings (Products), Mechanical properties, Reactor vessels
Proceedings Papers

Experimental Studies and Mechanical Properties Analysis of Three-Dimensional Oblique Rotating Friction Seismic Isolators

Saifeng Wu, Wenguang Liu, Wenfu He
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A045, August 8–12, 2022
Paper No: ICONE29-92541
DOI: https://doi.org/10.1115/ICONE29-92541
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Topics: Friction, Mechanical properties, Bearings, Damage, Deformation, Design, Earthquakes, Errors, Rubber, Stiffness
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

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

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

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

Determination of Fracture Toughness From Small Punch Test Using Inverse Finite Element Method for In-Service Equipment

Kaishu Guan, Tong Xu, Linling Guo, Mingxue Fu, Huadong Zhu
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A034, July 2–6, 2017
Paper No: ICONE25-67406
DOI: https://doi.org/10.1115/ICONE25-67406
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Topics: Finite element methods, Fracture toughness, Displacement, Stress, Pressure equipment, Mechanical properties, Databases, Mechanical testing, Artificial neural networks, Computer simulation
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)