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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

Paper No: ICONE28-64784

DOI: https://doi.org/10.1115/ICONE28-64784

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Topics: Design, Fatigue, Stress, Thermal stresses

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

Paper No: ICONE28-62333

DOI: https://doi.org/10.1115/ICONE28-62333

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Topics: Design, Fatigue, Pipes, Safety

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

Paper No: ICONE2020-16650

DOI: https://doi.org/10.1115/ICONE2020-16650

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Topics: Fatigue, Flow-induced vibrations, Fluids, Pressure vessels, Random vibration, Risk assessment

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

Paper No: ICONE2020-16948

DOI: https://doi.org/10.1115/ICONE2020-16948

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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

Paper No: ICONE2020-16426

DOI: https://doi.org/10.1115/ICONE2020-16426

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Topics: Boilers, Pressure, Transients (Dynamics), Valves, Pipes, Temperature, Collapse, Engineers, Fatigue, Flow (Dynamics)

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

Paper No: ICONE26-81095

DOI: https://doi.org/10.1115/ICONE26-81095

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Topics: Design, Pressure vessels, Stress, Failure mechanisms, Materials properties, Stress analysis (Engineering), Collapse, Constitutive equations, Failure, Fatigue

Proceedings Papers

CFD Thermal Analysis of ITER Pressure Suppression Tanks

Lorenzo Basili, Rosa Lo Frano, Marco Olcese, Igor Sekachev, Donato Aquaro

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A095, July 22–26, 2018

Paper No: ICONE26-82550

DOI: https://doi.org/10.1115/ICONE26-82550

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Topics: Computational fluid dynamics, Pressure, Thermal analysis, Stress, Thermal insulation, Vacuum, Vessels, Design, Fatigue, Fusion reactors

Proceedings Papers

Numerical Study of the Amplitude and the Convection Speed of Periodic Large-Scale Vortices in a Square Array of Cylinders Subjected to Axial Flow

Laurent De Moerloose, Jeroen De Ridder, Jan Vierendeels, Joris Degroote

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A023, July 22–26, 2018

Paper No: ICONE26-81730

DOI: https://doi.org/10.1115/ICONE26-81730

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Topics: Axial flow, Convection, Cylinders, Vortices, Pressure, Flow instability, Fluctuations (Physics), Approximation, Boundary-value problems, Engineering simulation

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

Paper No: ICONE26-81143

DOI: https://doi.org/10.1115/ICONE26-81143

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Topics: Cavity flows, Evaluation methods, Pipes, Thermal stratification, Flow (Dynamics), Water, Fatigue, High temperature, Temperature, Temperature profiles

Proceedings Papers

Development of Evaluation Method for Thermal Stratification by Cavity Flow in a Vertical Branch Pipe With Elbow and Horizontal Section: Modeling of Evaluation Method

Atsushi Kodama, Yoshiteru Komuro, Keiichi Hori, Hironori Noguchi, Yoshiyuki Kondo, Koichi Tanimoto

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A015, July 22–26, 2018

Paper No: ICONE26-81144

DOI: https://doi.org/10.1115/ICONE26-81144

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Topics: Cavity flows, Evaluation methods, Modeling, Pipes, Thermal stratification, Fatigue, High temperature, Temperature, Water, Cycles

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

Paper No: ICONE26-82180

DOI: https://doi.org/10.1115/ICONE26-82180

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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

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

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

Paper No: ICONE26-82596

DOI: https://doi.org/10.1115/ICONE26-82596

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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

Paper No: ICONE26-81640

DOI: https://doi.org/10.1115/ICONE26-81640

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Topics: Carbon steel, Fatigue cracks, Pipes, Transients (Dynamics), Fracture (Materials), Stress, ASME Standards, Fatigue

Proceedings Papers

Thermal Fatigue Test on Dissimilar Welded Joint Between Gr.91 and 304SS

Takashi Wakai, Sumio Kobayashi, Shoichi Kato, Masanori Ando, Hideki Takasho

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A008, July 2–6, 2017

Paper No: ICONE25-66099

DOI: https://doi.org/10.1115/ICONE25-66099

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Topics: Fatigue testing, Welded joints, Steel, Fatigue damage, Creep, Evaluation methods, Fatigue, Fatigue cracks, Finite element analysis, Alloys

Proceedings Papers

Investigation of Thermal Fatigue Characteristics of Charging Line of RCV in PWR

Naeem Ahmad, XiangBin Li, Iftikhar Ahmad, Nan Li, Shahroze Ahmed, Ahmed Abdul Ghani Abdul Gayoum AlFadl

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A097, July 2–6, 2017

Paper No: ICONE25-67417

DOI: https://doi.org/10.1115/ICONE25-67417

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Topics: Fatigue, Pressurized water reactors, Nuclear power stations, Transients (Dynamics), Fatigue damage, Fluid structure interaction, Piping systems, Computational fluid dynamics, Control systems, Fatigue analysis

Proceedings Papers

Effect of Reactor Coolant Environment on Fatigue Property of Austenitic Stainless Steel in PWR

Fang Yonggang, Zhan Jiashuo, Chu Qibao, Wang Qing, Xu Yu

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A111, July 2–6, 2017

Paper No: ICONE25-67734

DOI: https://doi.org/10.1115/ICONE25-67734

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Topics: Fatigue properties, Nuclear reactor coolants, Pressurized water reactors, Stainless steel, Fatigue, Fatigue design, Coolants, Design, Fatigue analysis, Nuclear reactors

Proceedings Papers

Numerical Simulation for Effect of Rolling Motion on Thermal Stratification in a Surge Line

Y. L. Shen, Tao Lu, Bo Liu

Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A033, July 2–6, 2017

Paper No: ICONE25-67026

DOI: https://doi.org/10.1115/ICONE25-67026

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Topics: Computer simulation, Surges, Thermal stratification, Temperature, Computational fluid dynamics, Fluids, Pipes, Temperature distribution, Degrees of freedom, Fatigue

Proceedings Papers

Structural Integrity Assessment to Justify Increase in Upper Operating Temperature Limit of AGR Dome

Antony M. Hurst

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A067, July 2–6, 2017

Paper No: ICONE25-66859

DOI: https://doi.org/10.1115/ICONE25-66859

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Topics: Domes (Structural elements), Operating temperature, Temperature, Failure, Creep, Safety, Welded joints, Diaphragms (Mechanical devices), Diaphragms (Structural), Failure mechanisms

Proceedings Papers

Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP With Regard to Primary Water Stress Corrosion Cracking

Akihiro Mano, Yoshihito Yamaguchi, Jinya Katsuyama, Yinsheng Li

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A014, July 2–6, 2017

Paper No: ICONE25-66145

DOI: https://doi.org/10.1115/ICONE25-66145

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Topics: Fracture mechanics, Stress corrosion cracking, Water, Failure, Pipes, Probability, Fracture (Materials), Pressurized water reactors, Alloys, Boiling water reactors

2 3 4 5

NARROW

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

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

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

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

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

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

CFD Thermal Analysis of ITER Pressure Suppression Tanks

Numerical Study of the Amplitude and the Convection Speed of Periodic Large-Scale Vortices in a Square Array of Cylinders Subjected to Axial Flow

Development of Evaluation Method for Thermal Stratification by Cavity Flow in a Vertical Branch Pipe With Elbow and Horizontal Section: Experimental Results

Development of Evaluation Method for Thermal Stratification by Cavity Flow in a Vertical Branch Pipe With Elbow and Horizontal Section: Modeling of Evaluation Method

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

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

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

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

Thermal Fatigue Test on Dissimilar Welded Joint Between Gr.91 and 304SS

Investigation of Thermal Fatigue Characteristics of Charging Line of RCV in PWR

Effect of Reactor Coolant Environment on Fatigue Property of Austenitic Stainless Steel in PWR

Numerical Simulation for Effect of Rolling Motion on Thermal Stratification in a Surge Line

Structural Integrity Assessment to Justify Increase in Upper Operating Temperature Limit of AGR Dome

Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP With Regard to Primary Water Stress Corrosion Cracking

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