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Proceedings Papers

Study on the Response of Prestressed Reinforced Concrete Slabs With High Reinforcement Ratio Under Low Speed Impact

Mengyan Song, Di Jiang, Changkai Li, Chaoqi Zhang, Xudong Zhi

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A050, August 8–12, 2022

Paper No: ICONE29-92808

DOI: https://doi.org/10.1115/ICONE29-92808

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Topics: Concrete slabs, Reinforced concrete, Slabs, Displacement, Prestressed concrete, Containment, Nuclear power stations, Bonding, Computer software, Concretes

Proceedings Papers

Modal analysis and additional fluid mass of coaxial three-layer thin-wall member in annular flow gap

Chaofan Zhang, Daogang Lu, Yu Liu, Haotian Qiu

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A036, August 8–12, 2022

Paper No: ICONE29-92274

DOI: https://doi.org/10.1115/ICONE29-92274

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Topics: Cylinders, Flow (Dynamics), Fluids, Modal analysis, Thin wall structures, Fast neutron reactors, Shells, Pumps, Water, Clearances (Engineering)

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

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 of Neutron and Proton Displacement Damage in Ultra-Wide Bandgap Semiconductor Ga 2 O 3

Zhuang Shao, Ziqi Cai, Qingmin Zhang

Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A027, August 8–12, 2022

Paper No: ICONE29-92600

DOI: https://doi.org/10.1115/ICONE29-92600

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Topics: Damage, Displacement, Energy gap, Irradiation (Radiation exposure), Neutrons, Protons, Semiconductors (Materials), Simulation

Proceedings Papers

Estimation of Vibration Characteristics of Nuclear Facilities Based on Seismic Observation Records

Kouki Yamakawa, Masaaki Saruta, Hiroshi Moritani, Hiroaki Yamazaki, Akemi Nishida, Manabu Kawata, Kazuhiko Iigaki

Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A010, August 4–6, 2021

Paper No: ICONE28-64337

DOI: https://doi.org/10.1115/ICONE28-64337

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Topics: Nuclear power stations, Vibration, Displacement, Earthquakes, Excitation, Finite element model, Deformation, Pacific Ocean, Shorelines

Proceedings Papers

Using Pipe Whip Analysis via the Finite Element Method to Underpin the Delineation Between High and Moderate Energy Lines

Antony M. Hurst, Pavitra Bansal

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, V001T06A016, August 4–5, 2020

Paper No: ICONE2020-16474

DOI: https://doi.org/10.1115/ICONE2020-16474

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Topics: Finite element methods, Pipes, Underpinning, Hinges, Design, Finite element analysis, Light water reactors, Nuclear power stations, Nuclear reactor coolants, Stress

Proceedings Papers

Study on the Effect of Different Factors of Displacement Cascades in Alpha-Fe by Molecular Dynamics Simulations

Pandong Lin, Junfeng Nie, Meidan Liu

Paper No: ICONE2020-16161

DOI: https://doi.org/10.1115/ICONE2020-16161

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Topics: Cascades (Fluid dynamics), Displacement, Molecular dynamics simulation, Temperature

Proceedings Papers

Numerical Simulation of Bubble Dynamic Under Ocean Conditions

Chen Chong, Wang Mingjun, Tian Wenxi, Qiu Suizheng, Su Guanghui

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A041, July 22–26, 2018

Paper No: ICONE26-81639

DOI: https://doi.org/10.1115/ICONE26-81639

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Topics: Bubbles, Computer simulation, Oceans, Computational fluid dynamics, Containers, Displacement, Fluids, Nuclear power, Ocean waves, Ships

Proceedings Papers

Study on Flow Induced Vibration Analysis and Evaluation for Heat Transfer Tube of Steam Generator in Two Phase Flow

Huang Xuan, Qi Huan-huan, Cai Feng-chun, Feng Zhi-peng, Liu Shuai, Huang Qian

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A014, July 22–26, 2018

Paper No: ICONE26-81537

DOI: https://doi.org/10.1115/ICONE26-81537

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Topics: Boilers, Flow-induced vibrations, Heat transfer, Two-phase flow, Excitation, Fluids, Turbulence, Design, Displacement, Failure

Proceedings Papers

The Influence of Thermal Deformation on the Dynamic Characteristics of AMB Rotor of HTR-PM Helium Blower

Guowei Du, Jinpeng Yu, Hong Wang, Lei Zhao

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A004, July 22–26, 2018

Paper No: ICONE26-81132

DOI: https://doi.org/10.1115/ICONE26-81132

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Topics: Helium, Rotors, Thermal deformation, Temperature, Bearings, Computer simulation, Damping, Displacement, Electromagnetic force, Engines

Proceedings Papers

A Structural Integrity Assessment of a Nuclear Boiler Superheater Bifurcation at High Temperature

Brahim Nadri, Robert X. Wang

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A005, July 22–26, 2018

Paper No: ICONE26-81167

DOI: https://doi.org/10.1115/ICONE26-81167

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Topics: Bifurcation, Boilers, High temperature, Superheaters, Creep, Metals, Fatigue, Fracture (Materials), Safety, Boiler tubes

Proceedings Papers

Development of a Crack Opening Displacement Assessment Procedure Considering Change of Compliance at a Crack Part in Thin Wall Pipes Made of Modified 9Cr-1Mo Steel

Takashi Wakai, Hideo Machida, Manabu Arakawa, Seiji Yanagihara, Ryosuke Suzuki, Masaaki Matsubara

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A035, July 22–26, 2018

Paper No: ICONE26-82619

DOI: https://doi.org/10.1115/ICONE26-82619

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Topics: Displacement, Fracture (Materials), Pipes, Steel, Thin wall structures, Leakage, Sodium fast reactors, Sodium, Work hardening, Coolants

Proceedings Papers

Internal Vibration Source Analysis of AMB-Rotor System in HTR-PM Primary Helium Circulator

Jinpeng Yu, Lei Zhao

Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T04A008, July 22–26, 2018

Paper No: ICONE26-81339

DOI: https://doi.org/10.1115/ICONE26-81339

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Topics: Helium, Rotors, Vibration, Anisotropy, Errors, Accuracy and precision, Displacement measurement, Sensors, Displacement, Feedback

Proceedings Papers

Numerical and Experimental Investigation on Core Assembly Thermal-Gradient-Induced Deformation of Sodium-Cooled Fast Reactor

Zehua Ma, Yingwei Wu, G. H. Su, Wenxi Tian, Suizheng Qiu

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A063, July 22–26, 2018

Paper No: ICONE26-81891

DOI: https://doi.org/10.1115/ICONE26-81891

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Topics: Deformation, Manufacturing, Sodium fast reactors, Temperature gradient, Computation, Displacement, Finite element model, Friction, Reliability, Rods

Proceedings Papers

Analyzing the Impact of Solutes on PKA Spectrum for Simulation of Neutron Induced-Radiation Damage in Zr-Based Metals

Guang-bo Cai, Ya-dong Zhang, Yu-xiang Han, Jia-pei Yu

Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A041, July 22–26, 2018

Paper No: ICONE26-82132

DOI: https://doi.org/10.1115/ICONE26-82132

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Topics: Damage, Metals, Neutrons, Radiation (Physics), Simulation, Zirconium, Computer simulation, Alloys, Atoms, Spectra (Spectroscopy)

Proceedings Papers

Numerical Simulation of Safety Rod and its Drive Mechanism in Sodium-Cooled Fast Reactor During Scram Action

Li Yan, Hu Wenjun, Ren Lixia

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A052, July 22–26, 2018

Paper No: ICONE26-81559

DOI: https://doi.org/10.1115/ICONE26-81559

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Topics: Computer simulation, Safety, Scram, Sodium fast reactors, Accidents, China, Displacement, Fast neutron reactors, Flow (Dynamics), Pipes

Proceedings Papers

Sensitivity of CTF Solution to Subchannel Window Size

Roman Mukin, Marcus Seidl, Ivor Clifford, Hakim Ferroukhi

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A065, July 22–26, 2018

Paper No: ICONE26-82546

DOI: https://doi.org/10.1115/ICONE26-82546

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Topics: Critical heat flux, Displacement, Flow (Dynamics), Fuels, Heat flux, Modeling, Nucleate boiling, Pressurized water reactors

Proceedings Papers

A Flow-Induced Vibration Study on the Multiple Rectangular Tubes Bundles for Steam Generator Outlet Pipes of HTR-PM

Song Yu, Zhou Qin, Zhao Jiaqing, Zhang Yiyang, Wu Xinxin

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A018, July 22–26, 2018

Paper No: ICONE26-81229

DOI: https://doi.org/10.1115/ICONE26-81229

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Topics: Boilers, Flow-induced vibrations, Pipes, Cylinders, Vibration, High temperature, ASME Standards, Circular cylinders, Collisions (Physics), Damage

Proceedings Papers

Analytical Study on Fragility Evaluation With Uncertainty Against Fault Displacement for Nuclear Power Plant Buildings

Kenshiro Ishiki, Hirokazu Tsuji, Minoru Kanechika, Yoshinori Mihara

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A002, July 22–26, 2018

Paper No: ICONE26-81072

DOI: https://doi.org/10.1115/ICONE26-81072

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Topics: Displacement, Nuclear power stations, Structures, Uncertainty, Soil, Hazards, Accidents, Building materials, Chaos, Design

NARROW

Study on the Response of Prestressed Reinforced Concrete Slabs With High Reinforcement Ratio Under Low Speed Impact

Modal analysis and additional fluid mass of coaxial three-layer thin-wall member in annular flow gap

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

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

Simulation of Neutron and Proton Displacement Damage in Ultra-Wide Bandgap Semiconductor Ga 2 O 3

Estimation of Vibration Characteristics of Nuclear Facilities Based on Seismic Observation Records

Using Pipe Whip Analysis via the Finite Element Method to Underpin the Delineation Between High and Moderate Energy Lines

Study on the Effect of Different Factors of Displacement Cascades in Alpha-Fe by Molecular Dynamics Simulations

Numerical Simulation of Bubble Dynamic Under Ocean Conditions

Study on Flow Induced Vibration Analysis and Evaluation for Heat Transfer Tube of Steam Generator in Two Phase Flow

The Influence of Thermal Deformation on the Dynamic Characteristics of AMB Rotor of HTR-PM Helium Blower

A Structural Integrity Assessment of a Nuclear Boiler Superheater Bifurcation at High Temperature

Development of a Crack Opening Displacement Assessment Procedure Considering Change of Compliance at a Crack Part in Thin Wall Pipes Made of Modified 9Cr-1Mo Steel

Internal Vibration Source Analysis of AMB-Rotor System in HTR-PM Primary Helium Circulator

Numerical and Experimental Investigation on Core Assembly Thermal-Gradient-Induced Deformation of Sodium-Cooled Fast Reactor

Analyzing the Impact of Solutes on PKA Spectrum for Simulation of Neutron Induced-Radiation Damage in Zr-Based Metals

Numerical Simulation of Safety Rod and its Drive Mechanism in Sodium-Cooled Fast Reactor During Scram Action

Sensitivity of CTF Solution to Subchannel Window Size

A Flow-Induced Vibration Study on the Multiple Rectangular Tubes Bundles for Steam Generator Outlet Pipes of HTR-PM

Analytical Study on Fragility Evaluation With Uncertainty Against Fault Displacement for Nuclear Power Plant Buildings

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