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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

Paper No: ICONE29-93561

DOI: https://doi.org/10.1115/ICONE29-93561

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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

Paper No: ICONE29-90172

DOI: https://doi.org/10.1115/ICONE29-90172

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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

Paper No: ICONE29-93631

DOI: https://doi.org/10.1115/ICONE29-93631

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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

Paper No: ICONE29-92271

DOI: https://doi.org/10.1115/ICONE29-92271

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Topics: Fast neutron reactors, Fatigue, Fatigue analysis, Thermocouples

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

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

Paper No: ICONE29-93082

DOI: https://doi.org/10.1115/ICONE29-93082

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Topics: Brittle fracture, Finite element methods, Fracture (Materials), Fracture (Process), Nuclear power stations, Pipes, Radiation (Physics), Computer software, Engineering standards, Engineers

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

Paper No: ICONE29-93763

DOI: https://doi.org/10.1115/ICONE29-93763

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Topics: Alloys, Fatigue, Fatigue properties

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

Paper No: ICONE29-92926

DOI: https://doi.org/10.1115/ICONE29-92926

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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

Paper No: ICONE29-91662

DOI: https://doi.org/10.1115/ICONE29-91662

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Topics: Fatigue, Oscillations, Pipe flow, Pipelines, Principal component analysis, Thermal stratification

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

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

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

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

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

Robert Wang, Louis Chang, Tom Hurst, Antony Hurst

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

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

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

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

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

2 3 4 5

NARROW

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

On Multiaxial Strain Characteristics of Piping Systems Subjected to Earthquake Loads

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

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

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

A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant

Study on Fatigue Properties of Hydrided CZ2 Alloy

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

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

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

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

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

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

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

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

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

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

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