1-20 of 103
Displacement
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93230
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
Open the PDF for A Comparative Approach of a Seismic Response Analysis Based on Housner Model and Added Mass Model for a Nuclear Water Storage Tank in another window
Topics: Water, Water storage, Sloshing, Fluid structure interaction, Center of mass, Convection, Displacement, Dynamic response, Finite element analysis, Finite element model
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92039
https://doi.org/10.1115/ICONE29-92039
View Paper titled, Flow-Solid Coupling Analysis of Pressure Vessels on Floating Nuclear Power Plants
Open the PDF for Flow-Solid Coupling Analysis of Pressure Vessels on Floating Nuclear Power Plants in another window
Topics: Displacement, Flow (Dynamics), Fluid structure interaction, Nuclear power stations, Pressure vessels, Sloshing, Stress, Vessels, Fast neutron reactors, Reactor vessels
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92808
https://doi.org/10.1115/ICONE29-92808
View Paper titled, Study on the Response of Prestressed Reinforced Concrete Slabs With High Reinforcement Ratio Under Low Speed Impact
Open the PDF for Study on the Response of Prestressed Reinforced Concrete Slabs With High Reinforcement Ratio Under Low Speed Impact in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92274
https://doi.org/10.1115/ICONE29-92274
View Paper titled, Modal analysis and additional fluid mass of coaxial three-layer thin-wall member in annular flow gap
Open the PDF for Modal analysis and additional fluid mass of coaxial three-layer thin-wall member in annular flow gap in another window
Topics: Cylinders, Flow (Dynamics), Fluids, Modal analysis, Thin wall structures, Fast neutron reactors, Shells, Pumps, Water, Clearances (Engineering)
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92600
https://doi.org/10.1115/ICONE29-92600
View Paper titled, Simulation of Neutron and Proton Displacement Damage in Ultra-Wide Bandgap Semiconductor Ga 2 O 3
Open the PDF for Simulation of Neutron and Proton Displacement Damage in Ultra-Wide Bandgap Semiconductor Ga 2 O 3 in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64337
https://doi.org/10.1115/ICONE28-64337
View Paper titled, Estimation of Vibration Characteristics of Nuclear Facilities Based on Seismic Observation Records
Open the PDF for Estimation of Vibration Characteristics of Nuclear Facilities Based on Seismic Observation Records in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16474
https://doi.org/10.1115/ICONE2020-16474
View Paper titled, Using Pipe Whip Analysis via the Finite Element Method to Underpin the Delineation Between High and Moderate Energy Lines
Open the PDF for Using Pipe Whip Analysis via the Finite Element Method to Underpin the Delineation Between High and Moderate Energy Lines in another window
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
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, V001T06A006, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16161
https://doi.org/10.1115/ICONE2020-16161
View Paper titled, Study on the Effect of Different Factors of Displacement Cascades in Alpha-Fe by Molecular Dynamics Simulations
Open the PDF for Study on the Effect of Different Factors of Displacement Cascades in Alpha-Fe by Molecular Dynamics Simulations in another window
Topics: Cascades (Fluid dynamics), Displacement, Molecular dynamics simulation, Temperature
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82132
https://doi.org/10.1115/ICONE26-82132
View Paper titled, Analyzing the Impact of Solutes on PKA Spectrum for Simulation of Neutron Induced-Radiation Damage in Zr-Based Metals
Open the PDF for Analyzing the Impact of Solutes on PKA Spectrum for Simulation of Neutron Induced-Radiation Damage in Zr-Based Metals in another window
Topics: Damage, Metals, Neutrons, Radiation (Physics), Simulation, Zirconium, Computer simulation, Alloys, Atoms, Spectra (Spectroscopy)
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81891
https://doi.org/10.1115/ICONE26-81891
View Paper titled, Numerical and Experimental Investigation on Core Assembly Thermal-Gradient-Induced Deformation of Sodium-Cooled Fast Reactor
Open the PDF for Numerical and Experimental Investigation on Core Assembly Thermal-Gradient-Induced Deformation of Sodium-Cooled Fast Reactor in another window
Topics: Deformation, Manufacturing, Sodium fast reactors, Temperature gradient, Computation, Displacement, Finite element model, Friction, Reliability, Rods
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81639
https://doi.org/10.1115/ICONE26-81639
View Paper titled, Numerical Simulation of Bubble Dynamic Under Ocean Conditions
Open the PDF for Numerical Simulation of Bubble Dynamic Under Ocean Conditions in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81537
https://doi.org/10.1115/ICONE26-81537
View Paper titled, Study on Flow Induced Vibration Analysis and Evaluation for Heat Transfer Tube of Steam Generator in Two Phase Flow
Open the PDF for Study on Flow Induced Vibration Analysis and Evaluation for Heat Transfer Tube of Steam Generator in Two Phase Flow in another window
Topics: Boilers, Flow-induced vibrations, Heat transfer, Two-phase flow, Excitation, Fluids, Turbulence, Design, Displacement, Failure
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81559
https://doi.org/10.1115/ICONE26-81559
View Paper titled, Numerical Simulation of Safety Rod and its Drive Mechanism in Sodium-Cooled Fast Reactor During Scram Action
Open the PDF for Numerical Simulation of Safety Rod and its Drive Mechanism in Sodium-Cooled Fast Reactor During Scram Action in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82546
https://doi.org/10.1115/ICONE26-82546
View Paper titled, Sensitivity of CTF Solution to Subchannel Window Size
Open the PDF for Sensitivity of CTF Solution to Subchannel Window Size in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81229
https://doi.org/10.1115/ICONE26-81229
View Paper titled, A Flow-Induced Vibration Study on the Multiple Rectangular Tubes Bundles for Steam Generator Outlet Pipes of HTR-PM
Open the PDF for A Flow-Induced Vibration Study on the Multiple Rectangular Tubes Bundles for Steam Generator Outlet Pipes of HTR-PM in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81072
https://doi.org/10.1115/ICONE26-81072
View Paper titled, Analytical Study on Fragility Evaluation With Uncertainty Against Fault Displacement for Nuclear Power Plant Buildings
Open the PDF for Analytical Study on Fragility Evaluation With Uncertainty Against Fault Displacement for Nuclear Power Plant Buildings in another window
Topics: Displacement, Nuclear power stations, Structures, Uncertainty, Soil, Hazards, Accidents, Building materials, Chaos, Design
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81132
https://doi.org/10.1115/ICONE26-81132
View Paper titled, The Influence of Thermal Deformation on the Dynamic Characteristics of AMB Rotor of HTR-PM Helium Blower
Open the PDF for The Influence of Thermal Deformation on the Dynamic Characteristics of AMB Rotor of HTR-PM Helium Blower in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81167
https://doi.org/10.1115/ICONE26-81167
View Paper titled, A Structural Integrity Assessment of a Nuclear Boiler Superheater Bifurcation at High Temperature
Open the PDF for A Structural Integrity Assessment of a Nuclear Boiler Superheater Bifurcation at High Temperature in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82619
https://doi.org/10.1115/ICONE26-82619
View Paper titled, 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
Open the PDF for 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 in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81339
https://doi.org/10.1115/ICONE26-81339
View Paper titled, Internal Vibration Source Analysis of AMB-Rotor System in HTR-PM Primary Helium Circulator
Open the PDF for Internal Vibration Source Analysis of AMB-Rotor System in HTR-PM Primary Helium Circulator in another window
Topics: Helium, Rotors, Vibration, Anisotropy, Errors, Accuracy and precision, Displacement measurement, Sensors, Displacement, Feedback