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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
View Paper titled, A Comparative Approach of a Seismic Response Analysis Based on Housner Model and Added Mass Model for a Nuclear Water Storage Tank
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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
View Paper titled, Preliminary Study on Corrosion Behavior and Mechanical Properties Of Inconel 617 in Impure Helium Environment of VHTR
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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
View Paper titled, A Detailed Model to Predict Mechanical Characteristics of Fuel Assembly
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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
View Paper titled, Study on Properties of Aging and Immersion in Boric Acid Water of PEEK Insulation Material
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Topics: Insulation, Mechanical properties, Water
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
View Paper titled, Codes Comparative Study on Mechanical Properties of Core Forgings of Reactor Pressure Vessel
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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
View Paper titled, Experimental Studies and Mechanical Properties Analysis of Three-Dimensional Oblique Rotating Friction Seismic Isolators
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Topics: Friction, Mechanical properties, Bearings, Damage, Deformation, Design, Earthquakes, Errors, Rubber, Stiffness
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
View Paper titled, Microstructure, Texture and Mechanical Properties in Different Deformation Regions of the Compressed Zr-4 Alloy With Lamellar Structure
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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
View Paper titled, The Research on Welding Procedure and Performance of Zr-3 Thick Plate
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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
View Paper titled, Study on the Manufacturing Process of Large Super Alloy X-750 Forgings for Nuclear Equipment
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Topics: Alloys, Forging, Forgings (Products), Manufacturing, Springs, Temperature, Grain size, Annealing, Creep, Fracture (Materials)
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
View Paper titled, Investigation and Design of Energy-Absorbing Structure in Nuclear Fuel Cask
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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
View Paper titled, Finite Element Model to Simulate the Spacer Grid Buckling Characteristics
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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
View Paper titled, The Experimental Research on the Mechanical Characteristics of the Newly Designed Fuel Rod Supporting Structure of Spacer Grid
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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
View Paper titled, Evaluation of Irradiation Embrittlement of the Weld Metals in the Chinese RPV
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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
View Paper titled, Probability of Rupture for WWER-1000 Main Piping
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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
View Paper titled, Multiphysics Modeling of Thorium-Based (Th, U)O 2 and (Th, Pu)O 2 Fuel Performance in a Light Water Reactor
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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
View Paper titled, Analysis on the Dynamic Buckling Behavior of the Spacer Grid Structure
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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
View Paper titled, Additive Manufacturing of Spent Fuel Storage Rack Model by Selective Laser Melting
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Topics: Additive manufacturing, Lasers, Melting, Spent fuel storage, Manufacturing, Stainless steel, Economics , Mechanical properties, Nuclear power stations, Safety
Proceedings Papers

Heat Transfer Characteristics of Downward Facing Hot Horizontal Surfaces Using Mist Jet Impingement

Ashutosh Kumar Yadav, Parantak Sharma, Avadhesh Kumar Sharma, Mayank Modak, Vishal Nirgude, Santosh K. Sahu
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A099, July 2–6, 2017
Paper No: ICONE25-67537
DOI: https://doi.org/10.1115/ICONE25-67537
View Paper titled, Heat Transfer Characteristics of Downward Facing Hot Horizontal Surfaces Using Mist Jet Impingement
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Topics: Heat transfer, Cooling, Water, Emergency core cooling systems, Heat flux, Impingement cooling, Nozzles, Sprays, Steel, Accidents
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
View Paper titled, Tungsten Powder Filled Polymers for Flexible Radiation Shields in Nuclear Industries
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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
View Paper titled, 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
Click here to open pdf in another window PDF for 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
Topics: Arc welding, Electrodes, Flux (Metallurgy), Metals, Nickel, Irradiation (Radiation exposure), Mechanical properties, Protons, Dislocations, Ferrites (Magnetic materials)