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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

Research on the Technology Accuracy of the On-Line Fracture Assessment of Cracked Pipe in NPPs

Mingya Chen, Min Yu, Hongbo Gao, Shuang Qi, Lei Lin, Decheng Xu, Weiqiang Wang, Jinhua Shi, Qunjia Peng, Guodong Zhang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A003, August 8–12, 2022

Paper No: ICONE29-89057

DOI: https://doi.org/10.1115/ICONE29-89057

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Topics: Computer software, Fracture (Materials), Fracture (Process), Nuclear power stations, Pipes

Proceedings Papers

Research on Cracked Fuel Relocation of Dual-Cooled Annular Fuel Element Under Normal and LOCA Conditions

Yangbin Deng, Yuan Yin

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A022, August 8–12, 2022

Paper No: ICONE29-90755

DOI: https://doi.org/10.1115/ICONE29-90755

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Topics: Cracking (Materials), Discrete element methods, Fracture (Process), Fuels

Proceedings Papers

Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition

Jie Wang, Yang Wang, Jun Wei, Yongjun Deng

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A015, August 8–12, 2022

Paper No: ICONE29-90521

DOI: https://doi.org/10.1115/ICONE29-90521

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Topics: Cladding systems (Building), Ductility, Equipment performance, Hydrogen, Zirconium alloys, Zirconium, Accidents, Failure, Fracture (Process), Light water reactors

Proceedings Papers

Study of Iodine-Induced Stress Corrosion Cracking of CZ2 Alloy

Lin Shi, Changyuan Gao, Guoliang Zhang, Guocheng Sun, Xu Wang, Liutao Chen, Jun Tan

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A091, August 8–12, 2022

Paper No: ICONE29-93835

DOI: https://doi.org/10.1115/ICONE29-93835

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Topics: Alloys, Fracture (Materials), Fracture (Process), Stress corrosion cracking

Proceedings Papers

Numerical Study of the Effect of δ-Ferrite on Crack-Tip Mechanical Field

Yule Wu, Lefu Zhang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A060, August 8–12, 2022

Paper No: ICONE29-92656

DOI: https://doi.org/10.1115/ICONE29-92656

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Topics: Ferrites (Magnetic materials), Fracture (Materials), Stress, Cracking (Materials), Fracture (Process), Embrittlement, Finite element analysis, Finite element methods, Finite element model, High temperature

Proceedings Papers

Phase-Field Fracture Simulation of Dual-Cooled Annular Fuel Pellet

Wei Li

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A052, August 8–12, 2022

Paper No: ICONE29-92230

DOI: https://doi.org/10.1115/ICONE29-92230

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Topics: Fracture (Process), Fuels, Simulation

Proceedings Papers

The Effect of Nozzle Safe End Hot/Cold Wire Tungsten Inert Gas Buttering on Microstructure and Property

Chengdong Yang, Maolong Zhang, Xiangkun Ru, Weibao Tang

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A002, August 8–12, 2022

Paper No: ICONE29-89075

DOI: https://doi.org/10.1115/ICONE29-89075

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Topics: Cracking (Materials), Ductility, Fracture (Process), Nozzles, Tungsten, Wire, Grain boundaries, Grain size

Proceedings Papers

Research on Crack Resistance of Nuclear Grade Nickel-Based Alloy Welding Materials

Ying Ao, Changzheng Xu, Guo He, Zhanpeng Lv, Ping Zhu, Maolong Zhang, Jiasheng Zou

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A004, August 8–12, 2022

Paper No: ICONE29-89321

DOI: https://doi.org/10.1115/ICONE29-89321

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Topics: Alloys, Crystals, Ductility, Fracture (Materials), Fracture (Process), Nickel, Stress corrosion cracking, Welding

Proceedings Papers

Evaluation on Weldability of Nickel-Base Alloy Weld Materials With High Chromium Content

Yoshinori Katayama, Takahiro Hayashi, Daiki Tanaka, Hidenori Takahashi

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A003, August 8–12, 2022

Paper No: ICONE29-89096

DOI: https://doi.org/10.1115/ICONE29-89096

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Topics: Alloys, Cracking (Materials), Ductility, Fracture (Process), Nickel, Solidification

Proceedings Papers

Optimizing Material/Component Fabrication Processing for Improving Service Performance in Nuclear Power Plant Coolants

Zhanpeng Lu

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A030, August 8–12, 2022

Paper No: ICONE29-92321

DOI: https://doi.org/10.1115/ICONE29-92321

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Topics: Coolants, Cracking (Materials), Fracture (Process), Manufacturing, Nuclear power stations, Pressurized water reactors, Stress corrosion cracking

Proceedings Papers

Research on Compliance Between Large Break LOCA of HPR1000 and New LOCA Acceptance Criterion 10CFR50.46c

Wang Weiwei, Yang Jiang, Lin Zhikang, Lu Xianghui, Zhang Ying, Shen Ting

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A010, August 8–12, 2022

Paper No: ICONE29-89155

DOI: https://doi.org/10.1115/ICONE29-89155

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Topics: Cladding systems (Building), Embrittlement, Fracture (Materials), Fracture (Process), Fuels, Hydrogen, Nuclear power stations, Oxidation, Oxygen, Safety

Proceedings Papers

Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development

Guoqiang Wang, William A. Byers, Zeses Karoutas

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A041, August 4–6, 2021

Paper No: ICONE28-66591

DOI: https://doi.org/10.1115/ICONE28-66591

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Topics: Accidents, Cladding systems (Building), Critical heat flux, Fuels, Chemistry, Pressurized water reactors, Coolants, Electrical resistivity, Film boiling, Heat flux

Proceedings Papers

Investigation on Solidification Behavior of Deposited Metal by GTAW With ERNiCrFe-13 Wire

Xiao Guo, Kai Xu, Xiaochun Lv, Peiyin Chen, Bo Chen, Shubin Huo

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, V003T10A001, August 4–6, 2021

Paper No: ICONE28-63770

DOI: https://doi.org/10.1115/ICONE28-63770

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Topics: Gas tungsten arc welding, Metals, Solidification, Wire, Temperature, Cracking (Materials), Fracture (Process), Differential scanning calorimetry, Ductility, Lasers

Proceedings Papers

Numerical Impact Simulation of Aircraft Into Reinforced Concrete Walls With Different Thickness

Kazuma Hirosaka, Hidekazu Takazawa, Katsumasa Miyazaki, Norihide Tohyama, Hiroyuki Nouji, Naomi Matsumoto

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A047, July 22–26, 2018

Paper No: ICONE26-82616

DOI: https://doi.org/10.1115/ICONE26-82616

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Topics: Aircraft, Reinforced concrete, Simulation, Phantoms, Concrete walls, Simulation models, Computer simulation, Damage, Impact testing, Kinematics

Proceedings Papers

New Needs of Fracture Mechanic Analysis at Design and Operation Level: Status of French Nuclear Mechanical Codes

Claude Faidy

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A002, July 22–26, 2018

Paper No: ICONE26-81096

DOI: https://doi.org/10.1115/ICONE26-81096

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Topics: Design, Fracture (Materials), Fracture (Process), Boilers, Brittle fracture, Brittleness, Failure, In-service inspection, Leak-before-break, Manufacturing

Proceedings Papers

A Theoretical Model of the Stress Intensity Factor Threshold of DHC for Fuel Cladding Tube

Liang Chen, Lili Liu, Xiaoming Song, Hua Pang

Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A031, July 22–26, 2018

Paper No: ICONE26-81665

DOI: https://doi.org/10.1115/ICONE26-81665

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Topics: Cladding systems (Building), Fuels, Stress, Temperature, Fracture (Materials), Temperature gradient, Cracking (Materials), Diffusion (Physics), Fracture (Process), Hydrogen

Proceedings Papers

First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM

Alessandro Scolaro, Ivor Clifford, Carlo Fiorina, Andreas Pautz

Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A051, July 22–26, 2018

Paper No: ICONE26-82381

DOI: https://doi.org/10.1115/ICONE26-82381

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Topics: Nuclear fuels, Temperature, Electrical conductance, Fuels, Materials properties, Cracking (Materials), Creep, Databases, Fracture (Process), Fuel rods

Proceedings Papers

Thermal Hydraulic Analysis of Pressurized Thermal Shock for Loviisa NPP Using Apros Simulation Code

Gintaras Žemulis, Pasi Junninen, Petri Kytömäki

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A051, July 22–26, 2018

Paper No: ICONE26-81558

DOI: https://doi.org/10.1115/ICONE26-81558

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Topics: Nuclear power stations, Simulation, Thermal shock, Safety, Emergencies, Reactor vessels, Embrittlement, Heat, Boundary-value problems, Cooling

2 3 4 5

NARROW

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

Research on the Technology Accuracy of the On-Line Fracture Assessment of Cracked Pipe in NPPs

Research on Cracked Fuel Relocation of Dual-Cooled Annular Fuel Element Under Normal and LOCA Conditions

Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition

Study of Iodine-Induced Stress Corrosion Cracking of CZ2 Alloy

Numerical Study of the Effect of δ-Ferrite on Crack-Tip Mechanical Field

Phase-Field Fracture Simulation of Dual-Cooled Annular Fuel Pellet

The Effect of Nozzle Safe End Hot/Cold Wire Tungsten Inert Gas Buttering on Microstructure and Property

Research on Crack Resistance of Nuclear Grade Nickel-Based Alloy Welding Materials

Evaluation on Weldability of Nickel-Base Alloy Weld Materials With High Chromium Content

Optimizing Material/Component Fabrication Processing for Improving Service Performance in Nuclear Power Plant Coolants

Research on Compliance Between Large Break LOCA of HPR1000 and New LOCA Acceptance Criterion 10CFR50.46c

Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development

Investigation on Solidification Behavior of Deposited Metal by GTAW With ERNiCrFe-13 Wire

Numerical Impact Simulation of Aircraft Into Reinforced Concrete Walls With Different Thickness

New Needs of Fracture Mechanic Analysis at Design and Operation Level: Status of French Nuclear Mechanical Codes

A Theoretical Model of the Stress Intensity Factor Threshold of DHC for Fuel Cladding Tube

First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM

Thermal Hydraulic Analysis of Pressurized Thermal Shock for Loviisa NPP Using Apros Simulation Code

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