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Proceedings Papers

Seismic Analysis of the Scale Reactor Structure Model of a Lead-Bismuth-Cooled ADS Reactor

Gang Rong, He Zhu, Yi Yang

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A017, August 8–12, 2022

Paper No: ICONE29-91753

DOI: https://doi.org/10.1115/ICONE29-91753

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Topics: Seismic analysis, Annulus, Design, Fluid structure interaction, Leakage, Cavities, Finite element analysis, Fluids, Metals, Shells

Proceedings Papers

Study on Stress Prediction Method of Explosion-Proof Electric Heater in Nuclear Power Plant

Yiwei Chen, Jiashun Ruan, Yan Wang, Qiuhong Zhou, Haitao Li

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A041, August 8–12, 2022

Paper No: ICONE29-91519

DOI: https://doi.org/10.1115/ICONE29-91519

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Topics: Explosions, Nuclear power stations, Stress

Proceedings Papers

Design and Validation on Preload of Manway Bolt for Pressurizer of Nuclear Power Plant Under Hydrotest Condition

Tao Chen, Guangming Xiong, Guanhua Fu, Xiaolong Zhao, Defu Wang, Yongqiang Zhang, Enming Liang

Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A009, August 8–12, 2022

Paper No: ICONE29-91714

DOI: https://doi.org/10.1115/ICONE29-91714

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Topics: Design, Finite element analysis, Nuclear power stations, Stress, Bolted flanges, Flanges, Coolants, Engineering prototypes, Gaskets, Leakage

Proceedings Papers

Comparative Study on Creep-Fatigue Damage Assessment Between R5 Procedures and a Full Inelastic Analysis

Antony M. Hurst, Louis C. W. Chang, Nak-Kyun Cho

Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A008, August 8–12, 2022

Paper No: ICONE29-91707

DOI: https://doi.org/10.1115/ICONE29-91707

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Topics: Creep, Damage assessment, Fatigue, Inelastic analysis, Stress, Damage, Elastic analysis, Cracking (Materials), Fracture (Process), Geometry

Proceedings Papers

Research on Structural Optimization Technology of Fuel Assembly Parts Based on Topology and Optimal Design

Huabin Fan, Shiyin Xu, Huili Jia

Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A041, August 8–12, 2022

Paper No: ICONE29-93368

DOI: https://doi.org/10.1115/ICONE29-93368

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Topics: Design, Fuels, Manufacturing, Structural optimization, Topology, Nozzles, Pressure drop, Stress, Coolants, Flow (Dynamics)

Proceedings Papers

Research on Risk Assessment of Heavy Load Drops in Nuclear Power Plants

Chao Ma, Yiming Wang, Churan Feng, Jian Yang

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A002, August 8–12, 2022

Paper No: ICONE29-89056

DOI: https://doi.org/10.1115/ICONE29-89056

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Topics: Nuclear power stations, Probabilistic safety assessment, Risk assessment, Stress

Proceedings Papers

Affecting Factors and Aspects of Developing Nuclear Public Acceptance Strategies

Haomiao Lin

Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T15A004, August 8–12, 2022

Paper No: ICONE29-90522

DOI: https://doi.org/10.1115/ICONE29-90522

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Topics: Carbon, Climate change, Construction, Nuclear power, Safety, Stress, Sustainable development

Proceedings Papers

Dynamic Modeling and Reactor Power Control of a Natural Circulation Pool-Type Lead-Cooled Fast Reactor

Yun Feng, Pei-Wei Sun, Xinyu Wei

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A104, August 8–12, 2022

Paper No: ICONE29-92872

DOI: https://doi.org/10.1115/ICONE29-92872

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Topics: Dynamic modeling, Fast neutron reactors, Control systems, Stress, Circuits, Design, Thermal energy, Coolants, Cooling, Flow (Dynamics)

Proceedings Papers

Flow-Solid Coupling Analysis of Pressure Vessels on Floating Nuclear Power Plants

Yuchao Wang, Daogang Lu, Fei Zhao, Yu Liu

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A071, August 8–12, 2022

Paper No: ICONE29-92039

DOI: https://doi.org/10.1115/ICONE29-92039

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Topics: Displacement, Flow (Dynamics), Fluid structure interaction, Nuclear power stations, Pressure vessels, Sloshing, Stress, Vessels, Fast neutron reactors, Reactor vessels

Proceedings Papers

Application of Probabilistic Safety Analysis in Analysis of Impact of Fangjiashan Nuclear Power Plant’s Load-Following Operation

Deyi Liu, Sixing Zha, Jian Wu, Yong Cao, Honghao Chen

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A001, August 8–12, 2022

Paper No: ICONE29-88835

DOI: https://doi.org/10.1115/ICONE29-88835

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Topics: Nuclear power, Probabilistic safety assessment, Stress

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

Simulation Analysis of Main and Auxiliary Switching and Motor Starting in Nuclear Power Plants

Zhang Xingzhen, Sun Hui

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A052, August 8–12, 2022

Paper No: ICONE29-92755

DOI: https://doi.org/10.1115/ICONE29-92755

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Topics: Motors, Nuclear power stations, Simulation, Simulation analysis, Stress

Proceedings Papers

Study on Analysis Method of LOCA Dynamic Response for Steam Generator Heat Transfer Tube

Xifeng Lu, Furui Xiong, Xinjun Wang, Honglei Ai, Bingjin Li, Xuejiao Shao, Kang Yang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A017, August 8–12, 2022

Paper No: ICONE29-90677

DOI: https://doi.org/10.1115/ICONE29-90677

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Topics: Boilers, Dynamic response, Heat transfer, Time-domain analysis, Stress, Modal analysis, Dynamic response analysis, Emission spectroscopy, Finite element model, Frequency-domain analysis

Proceedings Papers

Feasibility Study on Power Ramp Test Under Atmospheric Pressure and Ordinary Temperature

Xiangyu Wei, Wenhua Zhang, Yingchun Zhao

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A079, August 8–12, 2022

Paper No: ICONE29-93417

DOI: https://doi.org/10.1115/ICONE29-93417

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Topics: Atmospheric pressure, Fuels, Ropes, Temperature, Cladding systems (Building), Stress, Fuel rods, Irradiation (Radiation exposure), Pressure, Sensitivity analysis

Proceedings Papers

Effect of Contact Stress on Fretting Corrosion Behavior of Alloy 690 Tube Exposed to Simulated Secondary Water

Wenhua Zhuang, Zhongli Han, Xianglong Guo, Lefu Zhang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A054, August 8–12, 2022

Paper No: ICONE29-92395

DOI: https://doi.org/10.1115/ICONE29-92395

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Topics: Alloys, Corrosion, Stress, Water, Wear

Proceedings Papers

Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition

Jie Wang, Yang Wang, Jun Wei, Yongjun Deng

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A015, August 8–12, 2022

Paper No: ICONE29-90521

DOI: https://doi.org/10.1115/ICONE29-90521

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Topics: Cladding systems (Building), Ductility, Equipment performance, Hydrogen, Zirconium alloys, Zirconium, Accidents, Failure, Fracture (Process), Light water reactors

Proceedings Papers

Study on Out-Pile Performance of CZ Zirconium Alloy Guide Tube

Changyuan Gao, Lin Shi, Guoliang Zhang, Yang Xu, Minli Chen, Liutao Chen, Jun Tan

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A089, August 8–12, 2022

Paper No: ICONE29-93816

DOI: https://doi.org/10.1115/ICONE29-93816

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Topics: Corrosion, Creep, Zirconium alloys, Alloys, Zirconium, Corrosion resistance, Stress, Temperature, Mechanical testing, Particulate matter

Proceedings Papers

Numerical Study of the Effect of δ-Ferrite on Crack-Tip Mechanical Field

Yule Wu, Lefu Zhang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A060, August 8–12, 2022

Paper No: ICONE29-92656

DOI: https://doi.org/10.1115/ICONE29-92656

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Topics: Ferrites (Magnetic materials), Fracture (Materials), Stress, Cracking (Materials), Fracture (Process), Embrittlement, Finite element analysis, Finite element methods, Finite element model, High temperature

Proceedings Papers

Drop Analyses and Verification of the Spent Nuclear Fuel Transportation Cask Under Hypothetical Accident Conditions

Guangdong Liu, Weiliang Wu, He Zhu, Qingjun Ma, Qipeng Li

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A042, August 8–12, 2022

Paper No: ICONE29-91927

DOI: https://doi.org/10.1115/ICONE29-91927

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Topics: Accidents, Spent nuclear fuels, Stress, Transportation systems

Proceedings Papers

Structural Design and Dynamic Analysis of the Heat Exchanger Used in Nuclear Fuel Test Loop

Huang Gang, Sun Sheng, Pan Liangming, Si Junping

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A059, August 8–12, 2022

Paper No: ICONE29-92625

DOI: https://doi.org/10.1115/ICONE29-92625

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Topics: Design, Dynamic analysis, Heat exchangers, Nuclear fuels, Stress, Structural design

NARROW

Seismic Analysis of the Scale Reactor Structure Model of a Lead-Bismuth-Cooled ADS Reactor

Study on Stress Prediction Method of Explosion-Proof Electric Heater in Nuclear Power Plant

Design and Validation on Preload of Manway Bolt for Pressurizer of Nuclear Power Plant Under Hydrotest Condition

Comparative Study on Creep-Fatigue Damage Assessment Between R5 Procedures and a Full Inelastic Analysis

Research on Structural Optimization Technology of Fuel Assembly Parts Based on Topology and Optimal Design

Research on Risk Assessment of Heavy Load Drops in Nuclear Power Plants

Affecting Factors and Aspects of Developing Nuclear Public Acceptance Strategies

Dynamic Modeling and Reactor Power Control of a Natural Circulation Pool-Type Lead-Cooled Fast Reactor

Flow-Solid Coupling Analysis of Pressure Vessels on Floating Nuclear Power Plants

Application of Probabilistic Safety Analysis in Analysis of Impact of Fangjiashan Nuclear Power Plant’s Load-Following Operation

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

Simulation Analysis of Main and Auxiliary Switching and Motor Starting in Nuclear Power Plants

Study on Analysis Method of LOCA Dynamic Response for Steam Generator Heat Transfer Tube

Feasibility Study on Power Ramp Test Under Atmospheric Pressure and Ordinary Temperature

Effect of Contact Stress on Fretting Corrosion Behavior of Alloy 690 Tube Exposed to Simulated Secondary Water

Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition

Study on Out-Pile Performance of CZ Zirconium Alloy Guide Tube

Numerical Study of the Effect of δ-Ferrite on Crack-Tip Mechanical Field

Drop Analyses and Verification of the Spent Nuclear Fuel Transportation Cask Under Hypothetical Accident Conditions

Structural Design and Dynamic Analysis of the Heat Exchanger Used in Nuclear Fuel Test Loop

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