1-20 of 117
Fatigue
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 Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant

Zihao Zheng, Wenxin Qiu, Yang Dai, Jiesheng Min
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A064, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93082
https://doi.org/10.1115/ICONE29-93082
View Paper titled, A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant
Open the PDF for A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant in another window
Topics: Brittle fracture, Finite element methods, Fracture (Materials), Fracture (Process), Nuclear power stations, Pipes, Radiation (Physics), Computer software, Engineering standards, Engineers
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91707
https://doi.org/10.1115/ICONE29-91707
View Paper titled, Comparative Study on Creep-Fatigue Damage Assessment Between R5 Procedures and a Full Inelastic Analysis
Open the PDF for Comparative Study on Creep-Fatigue Damage Assessment Between R5 Procedures and a Full Inelastic Analysis in another window
Topics: Creep, Damage assessment, Fatigue, Inelastic analysis, Stress, Damage, Elastic analysis, Cracking (Materials), Fracture (Process), Geometry
Proceedings Papers

Partially Averaged Navier Stokes Simulations of Turbulent Thermal Mixing in T-Junction

Ashhar Bilal, Puzhen Gao
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A054, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92926
https://doi.org/10.1115/ICONE29-92926
View Paper titled, Partially Averaged Navier Stokes Simulations of Turbulent Thermal Mixing in T-Junction
Open the PDF for Partially Averaged Navier Stokes Simulations of Turbulent Thermal Mixing in T-Junction in another window
Topics: Fatigue, Junctions, Simulation, Turbulence
Proceedings Papers

Principal Component Analysis on Tangential Oscillation of Thermal Stratification in Pipe-Flow

Dongwei Wei, Mi Zhou, Naiqiang Zhang
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A020, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91662
https://doi.org/10.1115/ICONE29-91662
View Paper titled, Principal Component Analysis on Tangential Oscillation of Thermal Stratification in Pipe-Flow
Open the PDF for Principal Component Analysis on Tangential Oscillation of Thermal Stratification in Pipe-Flow in another window
Topics: Fatigue, Oscillations, Pipe flow, Pipelines, Principal component analysis, Thermal stratification
Proceedings Papers

Overview of AFCEN Non-Linear Benchmark in China – Improving Rules for Vessel Ratcheting Evaluation

Yu Tan, Xuejiao Shao, Enming Liang, Shuchun Zuo, Feng Lv, Thomas Metais, Han Liu
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A015, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93561
https://doi.org/10.1115/ICONE29-93561
View Paper titled, Overview of AFCEN Non-Linear Benchmark in China – Improving Rules for Vessel Ratcheting Evaluation
Open the PDF for Overview of AFCEN Non-Linear Benchmark in China – Improving Rules for Vessel Ratcheting Evaluation in another window
Topics: China, Vessels, Bullets, Computational methods, Computer software, Evaluation methods, Fatigue, Fatigue analysis, Geometry, Nozzles
Proceedings Papers

On Multiaxial Strain Characteristics of Piping Systems Subjected to Earthquake Loads

Masaki Morishita, Akihito Otani
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A002, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90172
https://doi.org/10.1115/ICONE29-90172
View Paper titled, On Multiaxial Strain Characteristics of Piping Systems Subjected to Earthquake Loads
Open the PDF for On Multiaxial Strain Characteristics of Piping Systems Subjected to Earthquake Loads in another window
Topics: Cycles, Earthquake resistant design, Earthquakes, Fatigue, Pipes, Piping systems, Stress, Excitation, ASME Boiler and Pressure Vessel Code, Deformation
Proceedings Papers

Comparison of Numerical Analysis Methods of Coolant Environmental Fatigue Based on Strain Rate Control

Xuejiao Shao, Hai Xie, Yixiong Zhang, Furui Xiong, Xinjun Wang, Kaikai Shi, Mingda Yu, Xuan Huang
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A064, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93631
https://doi.org/10.1115/ICONE29-93631
View Paper titled, Comparison of Numerical Analysis Methods of Coolant Environmental Fatigue Based on Strain Rate Control
Open the PDF for Comparison of Numerical Analysis Methods of Coolant Environmental Fatigue Based on Strain Rate Control in another window
Topics: Coolants, Fatigue, Numerical analysis, Stainless steel
Proceedings Papers

Thermal Fatigue Analysis of Thermocouple Protector at the Core Outlet of Fast Reactor Under Thermal Striping

Yu Si, Zaojing Chen, Haoliang Zhong, Xiaofei Chen, Yading Zhang
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A076, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92271
https://doi.org/10.1115/ICONE29-92271
View Paper titled, Thermal Fatigue Analysis of Thermocouple Protector at the Core Outlet of Fast Reactor Under Thermal Striping
Open the PDF for Thermal Fatigue Analysis of Thermocouple Protector at the Core Outlet of Fast Reactor Under Thermal Striping in another window
Topics: Fast neutron reactors, Fatigue, Fatigue analysis, Thermocouples
Proceedings Papers

Study on Fatigue Properties of Hydrided CZ2 Alloy

Jieming Huang, Changyuan Gao, Liutao Chen, Xu Wang, Jun Tan
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A085, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93763
https://doi.org/10.1115/ICONE29-93763
View Paper titled, Study on Fatigue Properties of Hydrided CZ2 Alloy
Open the PDF for Study on Fatigue Properties of Hydrided CZ2 Alloy in another window
Topics: Alloys, Fatigue, Fatigue properties
Proceedings Papers

Study on Safety Class 2 Piping Fatigue Evaluation for 60 Years of Design Life

Dae-Geon Lee, Kyoung-Su Kim, Young-Hun Heo, Seong-Ho Cho, Hyeong-Wook Kim
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, V003T12A004, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-62333
https://doi.org/10.1115/ICONE28-62333
View Paper titled, Study on Safety Class 2 Piping Fatigue Evaluation for 60 Years of Design Life
Open the PDF for Study on Safety Class 2 Piping Fatigue Evaluation for 60 Years of Design Life in another window
Topics: Design, Fatigue, Pipes, Safety
Proceedings Papers

Comparative Study on Thermal Stress Analysis and Fatigue Curve in Stress and Fatigue Calculation of Nuclear Equipment

Xuejiao Shao, Hai Xie, Yixiong Zhang, Liping Zhang, Xiaolong Fu, Xue Mi, Hui Li
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, V001T02A031, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64784
https://doi.org/10.1115/ICONE28-64784
View Paper titled, Comparative Study on Thermal Stress Analysis and Fatigue Curve in Stress and Fatigue Calculation of Nuclear Equipment
Open the PDF for Comparative Study on Thermal Stress Analysis and Fatigue Curve in Stress and Fatigue Calculation of Nuclear Equipment in another window
Topics: Design, Fatigue, Stress, Thermal stresses
Proceedings Papers

Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Line Down Horizontal Elbow

Yue Zou, Brian Derreberry
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T09A011, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16948
https://doi.org/10.1115/ICONE2020-16948
View Paper titled, Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Line Down Horizontal Elbow
Open the PDF for Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Line Down Horizontal Elbow in another window
Topics: Coolants, Fatigue, Pressurized water reactors
Proceedings Papers

Investigating Structural Response of Pressure Reducing Valve of Supercritical Steam Generator System Under Cyclic Moments, Thermal Transient, and Pressure Loadings

Nak-Kyun Cho, Pavitra Bansal, Antony M. Hurst
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, V001T06A015, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16426
https://doi.org/10.1115/ICONE2020-16426
View Paper titled, Investigating Structural Response of Pressure Reducing Valve of Supercritical Steam Generator System Under Cyclic Moments, Thermal Transient, and Pressure Loadings
Open the PDF for Investigating Structural Response of Pressure Reducing Valve of Supercritical Steam Generator System Under Cyclic Moments, Thermal Transient, and Pressure Loadings in another window
Topics: Boilers, Pressure, Transients (Dynamics), Valves, Pipes, Temperature, Collapse, Engineers, Fatigue, Flow (Dynamics)
Proceedings Papers

Fatigue Risk Evaluation of a Pressure Vessel Plug Subject to Flow Induced Vibration

Robert Wang, Louis Chang, Tom Hurst, Antony Hurst
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, V001T06A017, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16650
https://doi.org/10.1115/ICONE2020-16650
View Paper titled, Fatigue Risk Evaluation of a Pressure Vessel Plug Subject to Flow Induced Vibration
Open the PDF for Fatigue Risk Evaluation of a Pressure Vessel Plug Subject to Flow Induced Vibration in another window
Topics: Fatigue, Flow-induced vibrations, Fluids, Pressure vessels, Random vibration, Risk assessment
Proceedings Papers

Nonlinear Analysis in Pressure Vessel Design Codes: Recommendations for Codified Rules Improvements

Claude Faidy
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A001, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81095
https://doi.org/10.1115/ICONE26-81095
View Paper titled, Nonlinear Analysis in Pressure Vessel Design Codes: Recommendations for Codified Rules Improvements
Open the PDF for Nonlinear Analysis in Pressure Vessel Design Codes: Recommendations for Codified Rules Improvements in another window
Topics: Design, Pressure vessels, Stress, Failure mechanisms, Materials properties, Stress analysis (Engineering), Collapse, Constitutive equations, Failure, Fatigue
Proceedings Papers

Stress and Fatigue Analysis of Thermal Shock for Cladding of Center Measurement Column Lower Head in the Fast Reactor Under Shutdown Condition

Shu Zheng, Daogang Lu, Qiong Cao, Chao Liu, Yunlong Ding, Yi Huang
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A069, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82596
https://doi.org/10.1115/ICONE26-82596
View Paper titled, Stress and Fatigue Analysis of Thermal Shock for Cladding of Center Measurement Column Lower Head in the Fast Reactor Under Shutdown Condition
Open the PDF for Stress and Fatigue Analysis of Thermal Shock for Cladding of Center Measurement Column Lower Head in the Fast Reactor Under Shutdown Condition in another window
Topics: Cladding systems (Building), Fast neutron reactors, Fatigue analysis, Stress, Thermal shock, Fatigue damage, Temperature, Coolants, Damage, Design
Proceedings Papers

Research on Simplified Method of Transients Combining and Loading in Fatigue Crack Growth Analysis of Carbon Steel Nuclear Piping

Zhenshun Liu, Hongdong Zhen
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A019, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81640
https://doi.org/10.1115/ICONE26-81640
View Paper titled, Research on Simplified Method of Transients Combining and Loading in Fatigue Crack Growth Analysis of Carbon Steel Nuclear Piping
Open the PDF for Research on Simplified Method of Transients Combining and Loading in Fatigue Crack Growth Analysis of Carbon Steel Nuclear Piping in another window
Topics: Carbon steel, Fatigue cracks, Pipes, Transients (Dynamics), Fracture (Materials), Stress, ASME Standards, Fatigue
Proceedings Papers

LBB Analysis on Nuclear-Class Pipes of Floating Nuclear Power Stations

Fan Bai, Yong Liu, Xingsheng Lao, Qi Xiao, Zhenxing Zhao, Jun Wu, Can Ma, Wang Wei
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A029, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82180
https://doi.org/10.1115/ICONE26-82180
View Paper titled, LBB Analysis on Nuclear-Class Pipes of Floating Nuclear Power Stations
Open the PDF for LBB Analysis on Nuclear-Class Pipes of Floating Nuclear Power Stations in another window
Topics: Nuclear power stations, Pipes, Fracture (Materials), Leakage, Design, Drilling, Fatigue, Finite element methods, Fracture mechanics, Leak-before-break
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 Evaluation Method for Thermal Stratification by Cavity Flow in a Vertical Branch Pipe With Elbow and Horizontal Section: Experimental Results

Atsushi Kodama, Yoshiteru Komuro, Keiichi Hori, Hironori Noguchi, Yoshiyuki Kondo, Koichi Tanimoto
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A014, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81143
https://doi.org/10.1115/ICONE26-81143
View Paper titled, Development of Evaluation Method for Thermal Stratification by Cavity Flow in a Vertical Branch Pipe With Elbow and Horizontal Section: Experimental Results
Open the PDF for Development of Evaluation Method for Thermal Stratification by Cavity Flow in a Vertical Branch Pipe With Elbow and Horizontal Section: Experimental Results in another window
Topics: Cavity flows, Evaluation methods, Pipes, Thermal stratification, Flow (Dynamics), Water, Fatigue, High temperature, Temperature, Temperature profiles