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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)