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Proceedings Papers

Effect of Carbon Content on the Resistance to Intergranular Corrosion of Alloy 800H

Qiang Zhong, Man Wang, Wen-Qiang Sun, Jun-Jie Wu, Jiong Qian, Sen-Sen Ning

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A023, August 8–12, 2022

Paper No: ICONE29-91676

DOI: https://doi.org/10.1115/ICONE29-91676

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Topics: Alloys, Carbon, Computer software, Corrosion, Precipitation, Simulation

Proceedings Papers

Effect of Contact Stress on Fretting Corrosion Behavior of Alloy 690 Tube Exposed to Simulated Secondary Water

Wenhua Zhuang, Zhongli Han, Xianglong Guo, Lefu Zhang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A054, August 8–12, 2022

Paper No: ICONE29-92395

DOI: https://doi.org/10.1115/ICONE29-92395

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Topics: Alloys, Corrosion, Stress, Water, Wear

Proceedings Papers

Creep Properties of FeCrAl Alloy at High Temperature Under Neutron Irradiation

Huan Yao, Tianzhou Ye, Junmei Wu, Yingwei Wu, Chunyu Yin, Ping Chen

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A005, August 8–12, 2022

Paper No: ICONE29-89079

DOI: https://doi.org/10.1115/ICONE29-89079

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Topics: Alloys, Creep, High temperature, Irradiation (Radiation exposure), Neutrons

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

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

Study on Out-Pile Performance of CZ Zirconium Alloy Guide Tube

Changyuan Gao, Lin Shi, Guoliang Zhang, Yang Xu, Minli Chen, Liutao Chen, Jun Tan

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A089, August 8–12, 2022

Paper No: ICONE29-93816

DOI: https://doi.org/10.1115/ICONE29-93816

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Topics: Corrosion, Creep, Zirconium alloys, Alloys, Zirconium, Corrosion resistance, Stress, Temperature, Mechanical testing, Particulate matter

Proceedings Papers

Study of Pre-Oxidization Law and Fretting Wear Resistance of CZ2 Alloy Cladding

Guocheng Sun, Shi Lin, Xu Wang, Liutao Chen

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A088, August 8–12, 2022

Paper No: ICONE29-93804

DOI: https://doi.org/10.1115/ICONE29-93804

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Topics: Alloys, Cladding systems (Building), Wear, Wear resistance

Proceedings Papers

Effect of a Cr 2 O 3 /A-Al 2 O 3 Coating on the Corrosion Behavior of Incoloy 800H Alloy in High Temperature Impure Helium

Haoxiang Li, Wei Zheng, Bin Du, Huaqiang Yin, Zhihao Hong, Long Wang, Xuedong He, Tao Ma, Xingtuan Yang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A016, August 8–12, 2022

Paper No: ICONE29-90536

DOI: https://doi.org/10.1115/ICONE29-90536

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Topics: Alloys, Carburization, Coating processes, Coatings, Corrosion, Helium, High temperature

Proceedings Papers

High Temperature Oxidation Kinetics of Zr-Sn-Nb Alloy and the Effect of Its Oxide Film Growth On Corrosion Resistance

Wanqian Zhao

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A083, August 8–12, 2022

Paper No: ICONE29-93520

DOI: https://doi.org/10.1115/ICONE29-93520

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Topics: Alloys, Corrosion resistance, High temperature, Oxidation, Tin, Zirconium, Zirconium alloys

Proceedings Papers

Oxidation Behaviour of CZ Alloys Under High Temperature Steam

Minli Chen, Changyuan Gao, Guoliang Zhang, Lin Shi, Liutao Chen, Jun Tan

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A087, August 8–12, 2022

Paper No: ICONE29-93795

DOI: https://doi.org/10.1115/ICONE29-93795

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Topics: Alloys, High temperature steam, Oxidation, Steam, Zirconium alloys

Proceedings Papers

Microstructual and Micro-Chemical Analysis of Zr Cladding Alloys on Corrosion and Creep Properties

Qing Yang Lv, Libin Zhang, Minli Chen, Changyuan Gao, Yang Xu, Liutao Chen, Jun Tan

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A086, August 8–12, 2022

Paper No: ICONE29-93770

DOI: https://doi.org/10.1115/ICONE29-93770

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Topics: Alloys, Annealing, Cladding systems (Building), Corrosion, Creep, Tin, Zirconium

Proceedings Papers

Development of an MPS Code for Corium Behavior Analysis

Lijun Jian, Hongfan Lu, Peng Yu, Yidan Yuan

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A013, August 8–12, 2022

Paper No: ICONE29-91422

DOI: https://doi.org/10.1115/ICONE29-91422

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Topics: Accidents, Alloys, Collapse, Deformation, Drops, Enthalpy, Fukushima nuclear disaster, Japan, 2011, Heat transfer, Melting, Oscillations

Proceedings Papers

Investigation on the Inspection Technology of GH3535 Alloy Butt Weld With Linear Array Probe

Xiaodan Yuan, Zhijun Li

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A036, August 8–12, 2022

Paper No: ICONE29-92754

DOI: https://doi.org/10.1115/ICONE29-92754

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Topics: Alloys, Inspection, Probes

Proceedings Papers

High-Temperature Deformation Constitutive Relationship of Zr-Sn-Nb Alloy for Nuclear Power

Yingqi Gao, Ben Wang, Jianguo Cao, Qianqian Luo, Yuan Cao, Zhihao Zhang, Lian Wang, Bo Gao

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A022, August 8–12, 2022

Paper No: ICONE29-92123

DOI: https://doi.org/10.1115/ICONE29-92123

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Topics: Alloys, Constitutive equations, Deformation, High temperature, Nuclear power, Temperature, Tin, Zirconium

Proceedings Papers

Microstructure, Texture and Mechanical Properties in Different Deformation Regions of the Compressed Zr-4 Alloy With Lamellar Structure

Jie Ren, Geping Li, Fusen Yuan, Ben Wang, Fuzhou Han, Muhammad Ali, Yingdong Zhang, Wenbin Guo, Bo Gao

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A027, August 8–12, 2022

Paper No: ICONE29-92283

DOI: https://doi.org/10.1115/ICONE29-92283

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Topics: Alloys, Deformation, Mechanical properties, Recrystallization, Texture (Materials), Zirconium

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

Research on Behavior of Migration for Molten Material in U-Al Alloy Fuels Under Severe Accident

Yuejian Luo, Jian Deng, Dahuan Zhu, Hongping Sun, Ming Zhang, Xiaoli Wu, Youyou Xu, Lili Liu, Wenzhen Hu, Qingan Xiang

Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A021, August 8–12, 2022

Paper No: ICONE29-93467

DOI: https://doi.org/10.1115/ICONE29-93467

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Topics: Accidents, Alloys, Computer simulation, Fuels

Proceedings Papers

Die Design and Process Study of Zr-4 Alloy Profile Extrusion

Peng Qi, Bo Gao, Zhihao Zhang, Jianming Yin

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A041, August 8–12, 2022

Paper No: ICONE29-92961

DOI: https://doi.org/10.1115/ICONE29-92961

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Topics: Alloys, Computer simulation, Design, Extruding, Zirconium, Zirconium alloys

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

Study on the Manufacturing Process of Large Super Alloy X-750 Forgings for Nuclear Equipment

Mei-fang Chen, Sheng-qiang Cao, Kai Dong

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A019, August 8–12, 2022

Paper No: ICONE29-91791

DOI: https://doi.org/10.1115/ICONE29-91791

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Topics: Alloys, Forging, Forgings (Products), Manufacturing, Springs, Temperature, Grain size, Annealing, Creep, Fracture (Materials)

NARROW

Effect of Carbon Content on the Resistance to Intergranular Corrosion of Alloy 800H

Effect of Contact Stress on Fretting Corrosion Behavior of Alloy 690 Tube Exposed to Simulated Secondary Water

Creep Properties of FeCrAl Alloy at High Temperature Under Neutron Irradiation

Study on Fatigue Properties of Hydrided CZ2 Alloy

Study of Iodine-Induced Stress Corrosion Cracking of CZ2 Alloy

Study on Out-Pile Performance of CZ Zirconium Alloy Guide Tube

Study of Pre-Oxidization Law and Fretting Wear Resistance of CZ2 Alloy Cladding

Effect of a Cr 2 O 3 /A-Al 2 O 3 Coating on the Corrosion Behavior of Incoloy 800H Alloy in High Temperature Impure Helium

High Temperature Oxidation Kinetics of Zr-Sn-Nb Alloy and the Effect of Its Oxide Film Growth On Corrosion Resistance

Oxidation Behaviour of CZ Alloys Under High Temperature Steam

Microstructual and Micro-Chemical Analysis of Zr Cladding Alloys on Corrosion and Creep Properties

Development of an MPS Code for Corium Behavior Analysis

Investigation on the Inspection Technology of GH3535 Alloy Butt Weld With Linear Array Probe

High-Temperature Deformation Constitutive Relationship of Zr-Sn-Nb Alloy for Nuclear Power

Microstructure, Texture and Mechanical Properties in Different Deformation Regions of the Compressed Zr-4 Alloy With Lamellar Structure

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

Research on Behavior of Migration for Molten Material in U-Al Alloy Fuels Under Severe Accident

Die Design and Process Study of Zr-4 Alloy Profile Extrusion

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

Study on the Manufacturing Process of Large Super Alloy X-750 Forgings for Nuclear Equipment

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